National Library of Energy BETA

Sample records for area nuclear material

  1. Nuclear Materials Focus Area Fiscal Year 2002 Mid Year Review

    SciTech Connect (OSTI)

    Thiel, Elizabeth Chilcote

    2002-05-01

    The Nuclear Materials Focus Area (NMFA) held its annual mid-year review on February 12 and 14, 2002, in Santa Fe, New Mexico. The purpose of this review was to examine both the technical aspects and the programmatic aspects of its technology development program. The focus area activities were reviewed by a panel consisting of personnel representing the end users of the technologies, and technical experts in nuclear materials. This year's review was somewhat different than in the past, as the stress was on how well the various projects being managed through the NMFA aligned with the two thrust areas and nine key goals and priorities recently issued by the Deputy Assistant Secretary for DOE's Office of Environmental Management (EM).

  2. Nuclear Materials Focus Area Fiscal Year 2002 Mid Year Review

    SciTech Connect (OSTI)

    Thiel, E.C.; Fuhrman, P.W.

    2002-05-30

    The Nuclear Materials Focus Area (NMFA) held its annual mid-year review on February 12 and 14, 2002, in Santa Fe, New Mexico. The purpose of this review was to examine both the technical aspects and the programmatic aspects of its technology development program. The focus area activities were reviewed by a panel consisting of personnel representing the end users of the technologies, and technical experts in nuclear materials. This year's review was somewhat different than in the past, as the stress was on how well the various projects being managed through the NMFA aligned with the two thrust areas and nine key goals and priorities recently issued by the Deputy Assistant Secretary for DOE's Office of Environmental Management (EM).

  3. Nuclear materials management overview

    SciTech Connect (OSTI)

    DiGiallonardo, D.A. )

    1988-01-01

    The true goal of Nuclear Materials MANAGEMENT (NMM) is the strategical and economical management of all nuclear materials. Nuclear Materials Management's role involves near-term and long-term planning, reporting, forecasting, and reviewing of inventories. This function is administrative in nature. it is a growing area in need of future definition, direction, and development. Improvements are required in program structure, the way residues and wastes are determined, how ''what is and what if'' questions are handled, and in overall decision-making methods.

  4. Nuclear materials management overview

    SciTech Connect (OSTI)

    DiGiallonardo, D.A.

    1988-01-01

    The true goal of Nuclear Materials Management (NMM) is the strategical and economical management of all nuclear materials. Nuclear Materials Management's role involves near-term and long-term planning, reporting, forecasting, and reviewing of inventories. This function is administrative in nature. It is a growing area in need of future definition, direction, and development. Improvements are required in program structure, the way residues and wastes are determined, how /open quotes/What is and what if/close quotes/ questions are handled, and in overall decision-making methods. 2 refs.

  5. nuclear material

    National Nuclear Security Administration (NNSA)

    width"300" >WASHINGTON, D.C. - The Department of Energy's (DOE) National Nuclear Security Administration (NNSA), in partnership with the Defense Threat Reduction...

  6. Nuclear Materials Disposition

    Broader source: Energy.gov [DOE]

    In fulfilling its mission, EM frequently manages and completes disposition of surplus nuclear materials and spent nuclear fuel.  These are not waste. They are nuclear materials no longer needed for...

  7. Material Disposal Areas

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Material Disposal Areas Material Disposal Areas Material Disposal Areas, also known as MDAs, are sites where material was disposed of below the ground surface in excavated pits, trenches, or shafts. Contact Environmental Communication & Public Involvement P.O. Box 1663 MS M996 Los Alamos, NM 87545 (505) 667-0216 Email Material Disposal Areas at LANL The following are descriptions and status updates of each MDA at LANL. To view a current fact sheet on the MDAs, click on LA-UR-13-25837 (pdf).

  8. Nuclear Materials Science

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    16 Nuclear Materials Science Our multidisciplinary expertise comprises the core actinide materials science and metallurgical capability within the nuclear weapons production and surveillance communities. Contact Us Group Leader David Pugmire (acting) Email Group Office (505) 667-4665 The evaluations performed by our group are essential for the nuclear weapons program as well as nuclear materials storage, forensics, and actinide fundamental science. The evaluations performed by our group are

  9. Absolute nuclear material assay

    DOE Patents [OSTI]

    Prasad, Manoj K.; Snyderman, Neal J.; Rowland, Mark S.

    2010-07-13

    A method of absolute nuclear material assay of an unknown source comprising counting neutrons from the unknown source and providing an absolute nuclear material assay utilizing a model to optimally compare to the measured count distributions. In one embodiment, the step of providing an absolute nuclear material assay comprises utilizing a random sampling of analytically computed fission chain distributions to generate a continuous time-evolving sequence of event-counts by spreading the fission chain distribution in time.

  10. Absolute nuclear material assay

    DOE Patents [OSTI]

    Prasad, Manoj K.; Snyderman, Neal J.; Rowland, Mark S.

    2012-05-15

    A method of absolute nuclear material assay of an unknown source comprising counting neutrons from the unknown source and providing an absolute nuclear material assay utilizing a model to optimally compare to the measured count distributions. In one embodiment, the step of providing an absolute nuclear material assay comprises utilizing a random sampling of analytically computed fission chain distributions to generate a continuous time-evolving sequence of event-counts by spreading the fission chain distribution in time.

  11. Management of Nuclear Materials

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2009-08-17

    To establish requirements for the lifecycle management of DOE owned and/or managed accountable nuclear materials. Cancels DOE O 5660.1B.

  12. Management of Nuclear Materials

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1994-05-26

    To establish requirements and procedures for the management of nuclear materials within the Department of Energy (DOE). Cancels DOE 5660.1A. Canceled by DOE O 410.2.

  13. Management of Nuclear Materials

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2009-08-17

    To establish requirements for the lifecycle management of DOE owned and/or managed accountable nuclear materials. Admin Chg 1 dated 4-10-2014, supersedes DOE O 410.2.

  14. Nuclear Material Packaging Manual

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2008-03-07

    The manual provides detailed packaging requirements for protecting workers from exposure to nuclear materials stored outside of an approved engineered contamination barrier. Does not cancel/supersede other directives. Certified 11-18-10.

  15. Nuclear Material Control and Accountability

    Energy Savers [EERE]

    DOE-STD-1194-2011 JUNE 2011 ──────────────── CHANGE NOTICE NO.2 DECEMBER 2012 ──────────────── CHANGE NOTICE NO.3 OCTOBER 2013 DOE STANDARD NUCLEAR MATERIALS CONTROL AND ACCOUNTABILITY U.S. Department of Energy AREA SANS Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. ATTACHMENT 1 Change Notice No. 3 DOE -STD-1194-2011 October 2013 Nuclear Materials Control and Accountability

  16. Nuclear Materials Control and Accountability

    Energy Savers [EERE]

    NOT MEASUREMENT SENSITIVE DOE-STD-1194-2011 JUNE 2011 ──────────────── CHANGE NOTICE NO.2 DECEMBER 2012 DOE STANDARD NUCLEAR MATERIALS CONTROL AND ACCOUNTABILITY U.S. Department of Energy AREA SANS Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. ATTACHMENT 1 Change Notice No. 2 DOE -STD-1194-2011 December 2012 Nuclear Materials Control and Accountability Table of Changes Page/Section Change Page 19/Section

  17. Nuclear & Radiological Material Removal | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    & Radiological Material Removal | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation...

  18. Material Disposal Areas

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    updates of each MDA at LANL. To view a current fact sheet on the MDAs, click on LA-UR-13-25837 (pdf). MDA A MDA A is a Hazard Category 2 nuclear facility comprised of a...

  19. Nuclear Material Variance Calculation

    Energy Science and Technology Software Center (OSTI)

    1995-01-01

    MAVARIC (Materials Accounting VARIance Calculations) is a custom spreadsheet that significantly reduces the effort required to make the variance and covariance calculations needed to determine the detection sensitivity of a materials accounting system and loss of special nuclear material (SNM). The user is required to enter information into one of four data tables depending on the type of term in the materials balance (MB) equation. The four data tables correspond to input transfers, output transfers,more » and two types of inventory terms, one for nondestructive assay (NDA) measurements and one for measurements made by chemical analysis. Each data entry must contain an identification number and a short description, as well as values for the SNM concentration, the bulk mass (or solution volume), the measurement error standard deviations, and the number of measurements during an accounting period. The user must also specify the type of error model (additive or multiplicative) associated with each measurement, and possible correlations between transfer terms. Predefined spreadsheet macros are used to perform the variance and covariance calculations for each term based on the corresponding set of entries. MAVARIC has been used for sensitivity studies of chemical separation facilities, fuel processing and fabrication facilities, and gas centrifuge and laser isotope enrichment facilities.« less

  20. Material Protection, Control, & Accounting | National Nuclear...

    National Nuclear Security Administration (NNSA)

    Nonproliferation Nuclear and Radiological Material Security Material Protection, Control, & Accounting Material Protection, Control, & Accounting NNSA implements material...

  1. Nuclear Material Removal | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Material Removal | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery Jobs Apply for Our Jobs Our Jobs Working at NNSA

  2. Nuclear Material Control and Accountability

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2011-06-27

    This Order establishes performance objectives, metrics, and requirements for developing, implementing, and maintaining a nuclear material control and accountability program within DOE/NNSA and for DOE-owned materials at other facilities that are exempt from licensing by the Nuclear Regulatory Commission. Cancels DOE M 470.4-6. Admin Chg 1, 8-3-11.

  3. Nuclear Material Control and Accountability

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2011-06-27

    The Order establishes performance objectives, metrics, and requirements for developing, implementing, and maintaining a nuclear material control and accountability (MC&A) program within the U.S. Department of Energy (DOE), including the National Nuclear Security Administration (NNSA), and for DOE owned materials at other facilities that are exempt from licensing by the Nuclear Regulatory Commission (NRC). Admin Chg 3, dated 5-15-15 supersedes Admin Chg 2.

  4. Nuclear Materials Science

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    (acting) Email Group Office (505) 667-4665 Find Expertise header Search our employee skills database The evaluations performed by our group are essential for the nuclear weapons...

  5. Nuclear Energy Advisory Committee Meeting Materials | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Nuclear Energy Advisory Committee Meeting Materials Nuclear Energy Advisory Committee Meeting Materials January 4, 2016 MEETING MATERIALS: DECEMBER 11, 2015 Westin Crystal City ...

  6. Nuclear Material Control and Accountability

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2005-08-26

    The manual establishes a program for the control and accountability of nuclear materials within the Department of Energy. Chg 1, dated 8-14-06. Canceled by DOE O 474.2.

  7. Nuclear Material Control and Accountability

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2005-08-26

    The manual establishes a program for the control and accountability of nuclear materials within the Department of Energy. Cancels: DOE M 474.1-1B DOE M 474.1-2A

  8. Material Science and Nuclear Science

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Material Science and Nuclear Science Material Science and Nuclear Science National security depends on science and technology. The United States relies on Los Alamos National Laboratory for the best of both. No place on Earth pursues a broader array of world-class scientific endeavors. The Lab's four Science Pillars harness capabilities for solutions to threats- on national and global scales. Contact thumbnail of Business Development Business Development Richard P. Feynman Center for Innovation

  9. Fundamentals of materials accounting for nuclear safeguards

    SciTech Connect (OSTI)

    Pillay, K.K.S.

    1989-04-01

    Materials accounting is essential to providing the necessary assurance for verifying the effectiveness of a safeguards system. The use of measurements, analyses, records, and reports to maintain knowledge of the quantities of nuclear material present in a defined area of a facility and the use of physical inventories and materials balances to verify the presence of special nuclear materials are collectively known as materials accounting for nuclear safeguards. This manual, prepared as part of the resource materials for the Safeguards Technology Training Program of the US Department of Energy, addresses fundamental aspects of materials accounting, enriching and complementing them with the first-hand experiences of authors from varied disciplines. The topics range from highly technical subjects to site-specific system designs and policy discussions. This collection of papers is prepared by more than 25 professionals from the nuclear safeguards field. Representing research institutions, industries, and regulatory agencies, the authors create a unique resource for the annual course titled ''Materials Accounting for Nuclear Safeguards,'' which is offered at the Los Alamos National Laboratory.

  10. Global Material Security | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    The mission of the Office of Global Material Security (GMS) is to help partner countries secure and account for nuclear weapons, weapons-useable nuclear and radiological materials, ...

  11. Materials challenges for nuclear systems

    SciTech Connect (OSTI)

    Allen, Todd; Busby, Jeremy; Meyer, Mitch; Petti, David

    2010-11-26

    The safe and economical operation of any nuclear power system relies to a great extent, on the success of the fuel and the materials of construction. During the lifetime of a nuclear power system which currently can be as long as 60 years, the materials are subject to high temperature, a corrosive environment, and damage from high-energy particles released during fission. The fuel which provides the power for the reactor has a much shorter life but is subject to the same types of harsh environments. This article reviews the environments in which fuels and materials from current and proposed nuclear systems operate and then describes how the creation of the Advanced Test Reactor National Scientific User Facility is allowing researchers from across the U.S. to test their ideas for improved fuels and materials.

  12. Nuclear Material Control and Accountability

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2011-06-27

    This Order establishes performance objectives, metrics, and requirements for developing, implementing, and maintaining a nuclear material control and accountability program within DOE/NNSA and for DOE-owned materials at other facilities that are exempt from licensing by the Nuclear Regulatory Commission. Cancels DOE M 470.4-6, Admin Chg 1, 8-26-05. Admin Chg 2, dated 11-19-12, cancels DOE M 474.2 Admin Chg 1. Admin Chg 3, dated 5-15-15, cancels Admin Chg 2.

  13. Radiation Effects in Nuclear Waste Materials

    SciTech Connect (OSTI)

    Weber, William J.

    2005-09-30

    The objective of this project is to develop a fundamental understanding of radiation effects in glasses and ceramics, as well as the influence of solid-state radiation effects on aqueous dissolution kinetics, which may impact the performance of nuclear waste forms and stabilized nuclear materials. This work provides the underpinning science to develop improved glass and ceramic waste forms for the immobilization and disposition of high-level tank waste, excess plutonium, plutonium residues and scrap, other actinides, and other nuclear waste streams. Furthermore, this work is developing develop predictive models for the performance of nuclear waste forms and stabilized nuclear materials. Thus, the research performed under this project has significant implications for the immobilization of High-Level Waste (HLW) and Nuclear Materials, two mission areas within the Office of Environmental Management (EM). With regard to the HLW mission, this research will lead to improved understanding of radiation-induced degradation mechanisms and their effects on dissolution kinetics, as well as development of predictive models for waste form performance. In the Nuclear Materials mission, this research will lead to improvements in the understanding of radiation effects on the chemical and structural properties of materials for the stabilization and long-term storage of plutonium, highly-enriched uranium, and other actinides. The research uses plutonium incorporation, ion-beam irradiation, and electron-beam irradiation to simulate the effects of alpha decay and beta decay on relevant glasses and ceramics. The research under this project has the potential to result in improved glass and ceramic materials for the stabilization and immobilization of high-level tank waste, plutonium residues and scraps, surplus weapons plutonium, highly-enriched uranium, other actinides, and other radioactive materials.

  14. Radiation Effects in Nuclear Waste Materials

    SciTech Connect (OSTI)

    Weber, William J.

    2005-06-01

    The objective of this project is to develop a fundamental understanding of radiation effects in glasses and ceramics, as well as the influence of solid-state radiation effects on aqueous dissolution kinetics, which may impact the performance of nuclear waste forms and stabilized nuclear materials. This work provides the underpinning science to develop improved glass and ceramic waste forms for the immobilization and disposition of high-level tank waste, excess plutonium, plutonium residues and scrap, other actinides, and other nuclear waste streams. Furthermore, this work is developing develop predictive models for the performance of nuclear waste forms and stabilized nuclear materials. Thus, the research performed under this project has significant implications for the immobilization of High-Level Waste (HLW) and Nuclear Materials, two mission areas within the Office of Environmental Management (EM). With regard to the HLW mission, this research will lead to improved understanding of radiation-induced degradation mechanisms and their effects on dissolution kinetics, as well as development of predictive models for waste form performance. In the Nuclear Materials mission, this research will lead to improvements in the understanding of radiation effects on the chemical and structural properties of materials for the stabilization and long-term storage of plutonium, highly-enriched uranium, and other actinides. The research uses plutonium incorporation, ion-beam irradiation, and electron-beam irradiation to simulate the effects of alpha decay and beta decay on relevant glasses and ceramics. The research under this project has the potential to result in improved glass and ceramic materials for the stabilization and immobilization of high-level tank waste, plutonium residues and scraps, surplus weapons plutonium, highly-enriched uranium, other actinides, and other radioactive materials.

  15. Materials challenges for nuclear systems

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Allen, Todd; Busby, Jeremy; Meyer, Mitch; Petti, David

    2010-11-26

    The safe and economical operation of any nuclear power system relies to a great extent, on the success of the fuel and the materials of construction. During the lifetime of a nuclear power system which currently can be as long as 60 years, the materials are subject to high temperature, a corrosive environment, and damage from high-energy particles released during fission. The fuel which provides the power for the reactor has a much shorter life but is subject to the same types of harsh environments. This article reviews the environments in which fuels and materials from current and proposed nuclearmore » systems operate and then describes how the creation of the Advanced Test Reactor National Scientific User Facility is allowing researchers from across the U.S. to test their ideas for improved fuels and materials.« less

  16. Special Nuclear Materials: EM Manages Plutonium, Highly Enriched Uranium

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    and Uranium-233 | Department of Energy Waste Management » Nuclear Materials & Waste » Special Nuclear Materials: EM Manages Plutonium, Highly Enriched Uranium and Uranium-233 Special Nuclear Materials: EM Manages Plutonium, Highly Enriched Uranium and Uranium-233 105-K building houses the K-Area Material Storage (KAMS) facility, designated for the consolidated storage of surplus plutonium at Savannah River Site pending disposition. The plutonium shipped to KAMS is sealed inside a

  17. NNSA: Securing Domestic Radioactive Material | National Nuclear...

    National Nuclear Security Administration (NNSA)

    nuclear material around the world within four years, calling the danger of a terrorist acquiring nuclear weapons "the most immediate and extreme threat to global security." ...

  18. Focus Areas | Critical Materials Institute

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Focus Areas FA 1: Diversifying Supply FA 2: Developing Substitutes FA 3: Improving Reuse and Recycling FA 4: Crosscutting Research

  19. Special nuclear material simulation device

    DOE Patents [OSTI]

    Leckey, John H.; DeMint, Amy; Gooch, Jack; Hawk, Todd; Pickett, Chris A.; Blessinger, Chris; York, Robbie L.

    2014-08-12

    An apparatus for simulating special nuclear material is provided. The apparatus typically contains a small quantity of special nuclear material (SNM) in a configuration that simulates a much larger quantity of SNM. Generally the apparatus includes a spherical shell that is formed from an alloy containing a small quantity of highly enriched uranium. Also typically provided is a core of depleted uranium. A spacer, typically aluminum, may be used to separate the depleted uranium from the shell of uranium alloy. A cladding, typically made of titanium, is provided to seal the source. Methods are provided to simulate SNM for testing radiation monitoring portals. Typically the methods use at least one primary SNM spectral line and exclude at least one secondary SNM spectral line.

  20. Nuclear and Radiological Material Security | National Nuclear...

    National Nuclear Security Administration (NNSA)

    This includes NNSA's work to advance physical protection standards for nuclear facilities and to strengthen nuclear safeguards, which are criteria for the physical security and the ...

  1. nuclear material | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response ...

  2. UNCLASSIFIED UNCLASSIFIED Nuclear Materials Management & Safeguards...

    National Nuclear Security Administration (NNSA)

    UNCLASSIFIED Nuclear Materials Management & Safeguards System CONTACT INFORMATION UPDATE REPORTING IDENTIFICATION SYMBOL (RIS) RIS: Address: Facility Name: CONTACTS Name Email:...

  3. Research Areas | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Stewardship Science Academic Alliances / Research Areas Research Areas Properties of Materials under Extreme Conditions and Hydrodynamics During open solicitations research proposals are solicited for grants and Centers of Excellence in the area of fundamental properties and response of materials under extreme conditions (condensed matter physics and materials science, hydrodynamics and fluid dynamics). Extreme conditions include material response when subjected to one or more of the following:

  4. Nuclear Materials Information Program | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    Information Program | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the...

  5. Nuclear Materials: Reconsidering Wastes and Assets - 13193

    SciTech Connect (OSTI)

    Michalske, T.A.

    2013-07-01

    The nuclear industry, both in the commercial and the government sectors, has generated large quantities of material that span the spectrum of usefulness, from highly valuable ('assets') to worthless ('wastes'). In many cases, the decision parameters are clear. Transuranic waste and high level waste, for example, have no value, and is either in a final disposition path today, or - in the case of high level waste - awaiting a policy decision about final disposition. Other materials, though discardable, have intrinsic scientific or market value that may be hidden by the complexity, hazard, or cost of recovery. An informed decision process should acknowledge the asset value, or lack of value, of the complete inventory of materials, and the structure necessary to implement the range of possible options. It is important that informed decisions are made about the asset value for the variety of nuclear materials available. For example, there is a significant quantity of spent fuel available for recycle (an estimated $4 billion value in the Savannah River Site's (SRS) L area alone); in fact, SRS has already blended down more than 300 metric tons of uranium for commercial reactor use. Over 34 metric tons of surplus plutonium is also on a path to be used as commercial fuel. There are other radiological materials that are routinely handled at the site in large quantities that should be viewed as strategically important and / or commercially viable. In some cases, these materials are irreplaceable domestically, and failure to consider their recovery could jeopardize our technological leadership or national defense. The inventories of nuclear materials at SRS that have been characterized as 'waste' include isotopes of plutonium, uranium, americium, and helium. Although planning has been performed to establish the technical and regulatory bases for their discard and disposal, recovery of these materials is both economically attractive and in the national interest. (authors)

  6. Statistical methods for nuclear material management

    SciTech Connect (OSTI)

    Bowen W.M.; Bennett, C.A.

    1988-12-01

    This book is intended as a reference manual of statistical methodology for nuclear material management practitioners. It describes statistical methods currently or potentially important in nuclear material management, explains the choice of methods for specific applications, and provides examples of practical applications to nuclear material management problems. Together with the accompanying training manual, which contains fully worked out problems keyed to each chapter, this book can also be used as a textbook for courses in statistical methods for nuclear material management. It should provide increased understanding and guidance to help improve the application of statistical methods to nuclear material management problems.

  7. Transportation of Nuclear Materials | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Transportation of Nuclear Materials Transportation of Nuclear Materials GC-52 provides legal advice to DOE on legal and regulatory requirements and standards for transportation of radioactive and hazardous materials. DOE has authority under the Atomic Energy Act of 1954 (AEA) to regulate activities related to the transportation of radioactive materials undertaken by DOE or on its behalf. DOE shipments generally are conducted in accordance with the requirements and standards of the Nuclear

  8. Control and Accountability of Nuclear Materials

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1993-02-12

    The order prescribes DOE minimum requirements and procedures for control and accountability of nuclear materials at DOE-owned and -leased facilities and DOE-owned nuclear materials at other facilities which are exempt from licensing by the Nuclear Regulatory Commission {NRC). Cancels DOE O 5633.3. Canceled by DOE O 5633.3B.

  9. Control and Accountability of Nuclear Materials

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1999-08-11

    DOE O 474.1 prescribes Department of Energy (DOE) requirements for nuclear material control and accountability (MC&A) for DOE-owned and -leased facilities and DOE-owned nuclear materials at other facilities which are exempt from licensing by the Nuclear Regulatory Commission (NRC). Cancels DOE 5633.3B

  10. Security robots for nuclear materials management

    SciTech Connect (OSTI)

    Deming, R.

    1986-01-01

    Robots have successfully invaded industry where they have replaced costly personnel performing their tasks cheaper and better in most cases. There may be a place for a unique class of robots, security robots, in nuclear materials management. Robots could be employed in the functions of general response, patrol and neutralizing dangerous situations. The last is perhaps most important. Ion Track Instruments of Burlington, Massachusetts has designed an excellent unit to protect life in hazardous situations. The unit can detect, disrupt or remove explosives. It can enter dangerous areas to reconnoiter the extent of danger. It can communicate with those in a dangerous area. It can fight fires or clean an area using a 2 1/2 inch, two man hose. If necessary, it can engage an adversary in a fire fight using a twelve gauge shot gun.

  11. Control and Accountability of Nuclear Materials

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2000-11-20

    To prescribe Department of Energy (DOE) requirements, including those for the National Nuclear Security Administration (NNSA), for nuclear material control and accountability (MC&A) for DOE-owned and -leased facilities and DOE-owned nuclear materials at other facilities that are exempt from licensing by the Nuclear Regulatory Commission (NRC). DOE N 251.60, dated 11-19-04, extends this directive until 11-19-05. Cancels DOE O 474.1.

  12. NNSA: Securing Domestic Radioactive Material | National Nuclear...

    National Nuclear Security Administration (NNSA)

    2011 In April 2009, President Obama outlined an ambitious agenda to secure vulnerable nuclear material around the world within four years, calling the danger of a terrorist...

  13. UNCLASSIFIED Nuclear Materials Management & Safeguards System

    National Nuclear Security Administration (NNSA)

    Nuclear Materials Management & Safeguards System CHANGE OF PROJECT NUMBER UPDATE PROJECT Project Number: Title: Date Valid: Date Deactivated: Classification Codes: Project Number:...

  14. The nuclear materials control technology briefing book

    SciTech Connect (OSTI)

    Hartwell, J.K.; Fernandez, S.J.

    1992-03-01

    As national and international interests in nuclear arms control and non-proliferation of nuclear weapons, intensify, it becomes ever more important that contributors be aware of the technologies available for the measurement and control of the nuclear materials important to nuclear weapons development. This briefing book presents concise, nontechnical summaries of various special nuclear material (SNM) and tritium production monitoring technologies applicable to the control of nuclear materials and their production. Since the International Atomic Energy Agency (IAEA) operates a multinational, on-site-inspector-based safeguards program in support of the Treaty on the Non-Proliferation of Nuclear Weapons (NPT), many (but not all) of the technologies reported in this document are in routine use or under development for IAEA safeguards.

  15. Control and Accountability of Nuclear Materials

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1994-09-07

    To prescribe the Department of Energy (DOE) minimum requirements and procedures for control and accountability of nuclear materials at DOE-owned and -leased facilities and DOE-owned nuclear materials at other facilities which are exempt from licensing by the Nuclear Regulatory Commission. Cancels DOE O 5633.2A and DOE O 5633.3A. Canceled by DOE O 474.1

  16. Nuclear Concrete Materials Database Phase I Development

    SciTech Connect (OSTI)

    Ren, Weiju; Naus, Dan J

    2012-05-01

    The FY 2011 accomplishments in Phase I development of the Nuclear Concrete Materials Database to support the Light Water Reactor Sustainability Program are summarized. The database has been developed using the ORNL materials database infrastructure established for the Gen IV Materials Handbook to achieve cost reduction and development efficiency. In this Phase I development, the database has been successfully designed and constructed to manage documents in the Portable Document Format generated from the Structural Materials Handbook that contains nuclear concrete materials data and related information. The completion of the Phase I database has established a solid foundation for Phase II development, in which a digital database will be designed and constructed to manage nuclear concrete materials data in various digitized formats to facilitate electronic and mathematical processing for analysis, modeling, and design applications.

  17. Scoping Materials | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Scoping Materials | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery Jobs Apply for Our Jobs Our Jobs Working at NNSA

  18. Defense Nuclear Material Stewardship Integrated Inventory Information Management System (IIIMS).

    SciTech Connect (OSTI)

    Aas, Christopher A.; Lenhart, James E.; Bray, Olin H.; Witcher, Christina Jenkin

    2004-11-01

    Sandia National Laboratories was tasked with developing the Defense Nuclear Material Stewardship Integrated Inventory Information Management System (IIIMS) with the sponsorship of NA-125.3 and the concurrence of DOE/NNSA field and area offices. The purpose of IIIMS was to modernize nuclear materials management information systems at the enterprise level. Projects over the course of several years attempted to spearhead this modernization. The scope of IIIMS was broken into broad enterprise-oriented materials management and materials forecasting. The IIIMS prototype was developed to allow multiple participating user groups to explore nuclear material requirements and needs in detail. The purpose of material forecasting was to determine nuclear material availability over a 10 to 15 year period in light of the dynamic nature of nuclear materials management. Formal DOE Directives (requirements) were needed to direct IIIMS efforts but were never issued and the project has been halted. When restarted, duplicating or re-engineering the activities from 1999 to 2003 is unnecessary, and in fact future initiatives can build on previous work. IIIMS requirements should be structured to provide high confidence that discrepancies are detected, and classified information is not divulged. Enterprise-wide materials management systems maintained by the military can be used as overall models to base IIIMS implementation concepts upon.

  19. INSPECTION REPORT Alleged Nuclear Material Control

    Broader source: Energy.gov (indexed) [DOE]

    Alleged Nuclear Material Control and Accountability Weaknesses at the Department of Energy's Portsmouth Project INS-O-15-04 May 2015 U.S. Department of Energy Office of Inspector...

  20. International safeguards: Accounting for nuclear materials

    SciTech Connect (OSTI)

    Fishbone, L.G.

    1988-09-28

    Nuclear safeguards applied by the International Atomic Energy Agency (IAEA) are one element of the non-proliferation regime'', the collection of measures whose aim is to forestall the spread of nuclear weapons to countries that do not already possess them. Safeguards verifications provide evidence that nuclear materials in peaceful use for nuclear-power production are properly accounted for. Though carried out in cooperation with nuclear facility operators, the verifications can provide assurance because they are designed with the capability to detect diversion, should it occur. Traditional safeguards verification measures conducted by inspectors of the IAEA include book auditing; counting and identifying containers of nuclear material; measuring nuclear material; photographic and video surveillance; and sealing. Novel approaches to achieve greater efficiency and effectiveness in safeguards verifications are under investigation as the number and complexity of nuclear facilities grow. These include the zone approach, which entails carrying out verifications for groups of facilities collectively, and randomization approach, which entails carrying out entire inspection visits some fraction of the time on a random basis. Both approaches show promise in particular situations, but, like traditional measures, must be tested to ensure their practical utility. These approaches are covered on this report. 15 refs., 16 figs., 3 tabs.

  1. Nuclear Materials Research and Technology/Los Alamos National...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Crown Ether Complex 6 "Excess" Nuclear Materials Hold Keys to Medicine, ... that culminates in plutonium. 2 Nuclear Materials Research and TechnologyLos ...

  2. Nuclear Materials Research and Technology/Los Alamos National...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ... dication (nitrogen atoms in blue). 2 Nuclear Materials Research and TechnologyLos ... A. Bartsch (Texas Tech University). 3 Nuclear Materials Research and TechnologyLos ...

  3. Nuclear Materials Technology Division/Los Alamos National Laboratory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    0 Publications Nuclear Fuels Ceramics Materials Charac- terization Synthesis Metallurgy ... As a partial fulfillment of this re- sponsibility, in October 1994, the Nuclear Materials ...

  4. Nuclear Materials Technology Division/Los Alamos National Laboratory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    plus a concentrated plutonium oxide that would be stored as special nuclear material. ... in the form of a concentrated plutonium oxide, will be stored as special nuclear material. ...

  5. Nuclear Materials Technology Division/Los Alamos National Laboratory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Technical Accomplish- ments for 1994 2 Nuclear Materials Technology DivisionLos Alamos ... Figure 1. Acid recycle and recovery system. 3 Nuclear Materials Technology DivisionLos ...

  6. Y-12 Removes Nuclear Materials from Two Facilities to Reduce...

    National Nuclear Security Administration (NNSA)

    Blog Home Field Offices Welcome to the NNSA Production Office NPO News Releases Y-12 Removes Nuclear Materials from Two Facilities ... Y-12 Removes Nuclear Materials from...

  7. Determination of leakage areas in nuclear piping

    SciTech Connect (OSTI)

    Keim, E.

    1997-04-01

    For the design and operation of nuclear power plants the Leak-Before-Break (LBB) behavior of a piping component has to be shown. This means that the length of a crack resulting in a leak is smaller than the critical crack length and that the leak is safely detectable by a suitable monitoring system. The LBB-concept of Siemens/KWU is based on computer codes for the evaluation of critical crack lengths, crack openings, leakage areas and leakage rates, developed by Siemens/KWU. In the experience with the leak rate program is described while this paper deals with the computation of crack openings and leakage areas of longitudinal and circumferential cracks by means of fracture mechanics. The leakage areas are determined by the integration of the crack openings along the crack front, considering plasticity and geometrical effects. They are evaluated with respect to minimum values for the design of leak detection systems, and maximum values for controlling jet and reaction forces. By means of fracture mechanics LBB for subcritical cracks has to be shown and the calculation of leakage areas is the basis for quantitatively determining the discharge rate of leaking subcritical through-wall cracks. The analytical approach and its validation will be presented for two examples of complex structures. The first one is a pipe branch containing a circumferential crack and the second one is a pipe bend with a longitudinal crack.

  8. Office of Weapons Material Protection | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy ... Material Management and Minimization Nonproliferation Proliferation Detection Material ...

  9. Nuclear fuel elements made from nanophase materials

    DOE Patents [OSTI]

    Heubeck, N.B.

    1998-09-08

    A nuclear reactor core fuel element is composed of nanophase high temperature materials. An array of the fuel elements in rod form are joined in an open geometry fuel cell that preferably also uses such nanophase materials for the cell structures. The particular high temperature nanophase fuel element material must have the appropriate mechanical characteristics to avoid strain related failure even at high temperatures, in the order of about 3000 F. Preferably, the reactor type is a pressurized or boiling water reactor and the nanophase material is a high temperature ceramic or ceramic composite. Nanophase metals, or nanophase metals with nanophase ceramics in a composite mixture, also have desirable characteristics, although their temperature capability is not as great as with all-ceramic nanophase material. Combinations of conventional or nanophase metals and conventional or nanophase ceramics can be employed as long as there is at least one nanophase material in the composite. The nuclear reactor so constructed has a number of high strength fuel particles, a nanophase structural material for supporting a fuel rod at high temperature, a configuration to allow passive cooling in the event of a primary cooling system failure, an ability to retain a coolable geometry even at high temperatures, an ability to resist generation of hydrogen gas, and a configuration having good nuclear, corrosion, and mechanical characteristics. 5 figs.

  10. Nuclear fuel elements made from nanophase materials

    DOE Patents [OSTI]

    Heubeck, Norman B.

    1998-01-01

    A nuclear reactor core fuel element is composed of nanophase high temperature materials. An array of the fuel elements in rod form are joined in an open geometry fuel cell that preferably also uses such nanophase materials for the cell structures. The particular high temperature nanophase fuel element material must have the appropriate mechanical characteristics to avoid strain related failure even at high temperatures, in the order of about 3000.degree. F. Preferably, the reactor type is a pressurized or boiling water reactor and the nanophase material is a high temperature ceramic or ceramic composite. Nanophase metals, or nanophase metals with nanophase ceramics in a composite mixture, also have desirable characteristics, although their temperature capability is not as great as with all-ceramic nanophase material. Combinations of conventional or nanophase metals and conventional or nanophase ceramics can be employed as long as there is at least one nanophase material in the composite. The nuclear reactor so constructed has a number of high strength fuel particles, a nanophase structural material for supporting a fuel rod at high temperature, a configuration to allow passive cooling in the event of a primary cooling system failure, an ability to retain a coolable geometry even at high temperatures, an ability to resist generation of hydrogen gas, and a configuration having good nuclear, corrosion, and mechanical characteristics.

  11. UNCLASSIFIED Nuclear Materials Management & Safeguards System

    National Nuclear Security Administration (NNSA)

    Nuclear Materials Management & Safeguards System CHANGE OF PROJECT NUMBER UPDATE PROJECT Project Number: Title: Date Valid: Date Deactivated: Classification Codes: Project Number: Project Title: Associated Materials: Programmatic RIS Previous Project Number(s) Status Code Allotment Code (S=Supplier, U=User) I authorize that the information listed above is for the NMMSS Program to use as part of the project number conversion process for this facility. Signature of Authorized Official Date

  12. Draft - DOE G 410.2-1, Nuclear Material Disposition

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    This document provides a roadmap for implementing the requirements for disposition of nuclear material as outlined in the U.S. Department of Energy (DOE) Order 410.2, Management of Nuclear Materials, and DOE Order 474.2, Nuclear Material Control and Accountability. This Guide provides the basic framework for the nuclear material disposition process, includes information related to the Programmatic Value Determination (PVD) process, and identifies Discard Limits (DL) for specific low-equity nuclear materials.

  13. Muon Tracking to Detect Special Nuclear Materials

    SciTech Connect (OSTI)

    Schwellenbach, D.; Dreesen, W.; Green, J. A.; Tibbitts, A.; Schotik, G.; Borozdin, K.; Bacon, J.; Midera, H.; Milner, C.; Morris, C.; Perry, J.; Barrett, S.; Perry, K.; Scott, A.; Wright, C.; Aberle, D.

    2013-03-18

    Previous experiments have proven that nuclear assemblies can be imaged and identified inside of shipping containers using vertical trajectory cosmic-ray muons with two-sided imaging. These experiments have further demonstrated that nuclear assemblies can be identified by detecting fission products in coincidence with tracked muons. By developing these technologies, advanced sensors can be designed for a variety of warhead monitoring and detection applications. The focus of this project is to develop tomographic-mode imaging using near-horizontal trajectory muons in conjunction with secondary particle detectors. This will allow imaging in-situ without the need to relocate the objects and will enable differentiation of special nuclear material (SNM) from other high-Z materials.

  14. Nuclear Material Control and Accountability System Effectiveness Tool (MSET)

    SciTech Connect (OSTI)

    Powell, Danny H; Elwood Jr, Robert H; Roche, Charles T; Campbell, Billy J; Hammond, Glenn A; Meppen, Bruce W; Brown, Richard F

    2011-01-01

    A nuclear material control and accountability (MC&A) system effectiveness tool (MSET) has been developed in the United States for use in evaluating material protection, control, and accountability (MPC&A) systems in nuclear facilities. The project was commissioned by the National Nuclear Security Administration's Office of International Material Protection and Cooperation. MSET was developed by personnel with experience spanning more than six decades in both the U.S. and international nuclear programs and with experience in probabilistic risk assessment (PRA) in the nuclear power industry. MSET offers significant potential benefits for improving nuclear safeguards and security in any nation with a nuclear program. MSET provides a design basis for developing an MC&A system at a nuclear facility that functions to protect against insider theft or diversion of nuclear materials. MSET analyzes the system and identifies several risk importance factors that show where sustainability is essential for optimal performance and where performance degradation has the greatest impact on total system risk. MSET contains five major components: (1) A functional model that shows how to design, build, implement, and operate a robust nuclear MC&A system (2) A fault tree of the operating MC&A system that adapts PRA methodology to analyze system effectiveness and give a relative risk of failure assessment of the system (3) A questionnaire used to document the facility's current MPC&A system (provides data to evaluate the quality of the system and the level of performance of each basic task performed throughout the material balance area [MBA]) (4) A formal process of applying expert judgment to convert the facility questionnaire data into numeric values representing the performance level of each basic event for use in the fault tree risk assessment calculations (5) PRA software that performs the fault tree risk assessment calculations and produces risk importance factor reports on the facility's MC&A (software widely used in the aerospace, chemical, and nuclear power industries) MSET was peer reviewed in 2007 and validated in 2008 by benchmark testing at the Idaho National Laboratory in the United States. The MSET documents were translated into Russian and provided to Rosatom in July of 2008, and MSET is currently being evaluated for potential application in Russian Nuclear Facilities.

  15. Microsoft PowerPoint - Nuclear Material Import Export License...

    National Nuclear Security Administration (NNSA)

    Material ImportExport License - Uses & Reporting processes Gary Langlie - Nuclear Regulatory Commission Karen Antizzo - Link Technologies Overview What is a Nuclear Regulatory ...

  16. Nuclear Materials Technology/Los Alamos National Laboratory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    to maintaining the safety and reliability of the weapons in the nuclear stockpile. ... Actinide Research Quarterly 2 Nuclear Materials TechnologyLos Alamos National Laboratory ...

  17. Nuclear Materials Technology Division/Los Alamos National Laboratory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Reduces the Nuclear Danger, Responds to National Need 6 Division Director Discusses Plutonium Future 8 NMT Designs and Fabricates Standards for Nuclear Material Assay 10 ...

  18. Nuclear Material Disposition | Y-12 National Security Complex

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    examples. Global Security Cooley joins Y-12's Global Security and Strategic Partnerships Manufacturing and Technical Services Nuclear Material Recovery Nuclear Detection and...

  19. Nuclear Resonance Fluorescence for Materials Assay

    SciTech Connect (OSTI)

    Quiter, Brian J.; Ludewigt, Bernhard; Mozin, Vladimir; Prussin, Stanley

    2009-06-29

    This paper discusses the use of nuclear resonance fluorescence (NRF) techniques for the isotopic and quantitative assaying of radioactive material. Potential applications include age-dating of an unknown radioactive source, pre- and post-detonation nuclear forensics, and safeguards for nuclear fuel cycles Examples of age-dating a strong radioactive source and assaying a spent fuel pin are discussed. The modeling work has ben performed with the Monte Carlo radiation transport computer code MCNPX, and the capability to simulate NRF has bee added to the code. Discussed are the limitations in MCNPX?s photon transport physics for accurately describing photon scattering processes that are important contributions to the background and impact the applicability of the NRF assay technique.

  20. Nuclear Resonance Fluorescence for Materials Assay

    SciTech Connect (OSTI)

    Quiter, Brian; Ludewigt, Bernhard; Mozin, Vladimir; Prussin, Stanley

    2009-06-05

    This paper discusses the use of nuclear resonance fluorescence (NRF) techniques for the isotopic and quantitative assaying of radioactive material. Potential applications include age-dating of an unknown radioactive source, pre- and post-detonation nuclear forensics, and safeguards for nuclear fuel cycles Examples of age-dating a strong radioactive source and assaying a spent fuel pin are discussed. The modeling work has ben performed with the Monte Carlo radiation transport computer code MCNPX, and the capability to simulate NRF has bee added to the code. Discussed are the limitations in MCNPX's photon transport physics for accurately describing photon scattering processes that are important contributions to the background and impact the applicability of the NRF assay technique.

  1. Bay Area | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery Jobs Apply for Our Jobs Our Jobs Working at NNSA Blog Home / Bay

  2. Nuclear Safety Specialist Functional Area Qualification Standard

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    ... exhibitions * Special assignments * On-the-job experience A description of suggested ... B) e.g., preparation, review andor recommendation for approval of nuclear basis safety ...

  3. Nuclear Fuels & Materials Spotlight Volume 4

    SciTech Connect (OSTI)

    I. J. van Rooyen,; T. M. Lillo; Y. Q. WU; P.A. Demkowicz; L. Scott; D.M. Scates; E. L. Reber; J. H. Jackson; J. A. Smith; D.L. Cottle; B.H. Rabin; M.R. Tonks; S.B. Biner; Y. Zhang; R.L. Williamson; S.R. Novascone; B.W. Spencer; J.D. Hales; D.R. Gaston; C.J. Permann; D. Anders; S.L. Hayes; P.C. Millett; D. Andersson; C. Stanek; R. Ali; S.L. Garrett; J.E. Daw; J.L. Rempe; J. Palmer; B. Tittmann; B. Reinhardt; G. Kohse; P. Ramuhali; H.T. Chien; T. Unruh; B.M. Chase; D.W. Nigg; G. Imel; J. T. Harris

    2014-04-01

    As the nation's nuclear energy laboratory, Idaho National Laboratory brings together talented people and specialized nuclear research capability to accomplish our mission. This edition of the Nuclear Fuels and Materials Division Spotlight provides an overview of some of our recent accomplishments in research and capability development. These accomplishments include: • The first identification of silver and palladium migrating through the SiC layer in TRISO fuel • A description of irradiation assisted stress corrosion testing capabilities that support commercial light water reactor life extension • Results of high-temperature safety testing on coated particle fuels irradiated in the ATR • New methods for testing the integrity of irradiated plate-type reactor fuel • Description of a 'Smart Fuel' concept that wirelessly provides real time information about changes in nuclear fuel properties and operating conditions • Development and testing of ultrasonic transducers and real-time flux sensors for use inside reactor cores, and • An example of a capsule irradiation test. Throughout Spotlight, you'll find examples of productive partnerships with academia, industry, and government agencies that deliver high-impact outcomes. The work conducted at Idaho National Laboratory helps to spur innovation in nuclear energy applications that drive economic growth and energy security. We appreciate your interest in our work here at INL, and hope that you find this issue informative.

  4. Research Areas | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Magnetized High Energy Density Plasma Physics Specific areas of interest include, but are ... Relativistic HED Plasmas and Intense Beam Physics Specific areas of interest include, but ...

  5. Recovery of fissile materials from nuclear wastes

    DOE Patents [OSTI]

    Forsberg, Charles W. (Oak Ridge, TN)

    1999-01-01

    A process for recovering fissile materials such as uranium, and plutonium, and rare earth elements, from complex waste feed material, and converting the remaining wastes into a waste glass suitable for storage or disposal. The waste feed is mixed with a dissolution glass formed of lead oxide and boron oxide resulting in oxidation, dehalogenation, and dissolution of metal oxides. Carbon is added to remove lead oxide, and a boron oxide fusion melt is produced. The fusion melt is essentially devoid of organic materials and halogens, and is easily and rapidly dissolved in nitric acid. After dissolution, uranium, plutonium and rare earth elements are separated from the acid and recovered by processes such as PUREX or ion exchange. The remaining acid waste stream is vitrified to produce a waste glass suitable for storage or disposal. Potential waste feed materials include plutonium scrap and residue, miscellaneous spent nuclear fuel, and uranium fissile wastes. The initial feed materials may contain mixtures of metals, ceramics, amorphous solids, halides, organic material and other carbon-containing material.

  6. Research Areas | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    High Energy Density Laboratory Plasmas / Research Areas Research Areas High Energy Density Laboratory Plasmas (HEDLP) Research Areas During open solicitations proposals are sought in the following subfields and cross-cutting areas of HEDLP: High Energy Density Hydrodynamics Specific areas of interest include, but are not limited to, turbulent mixing, probing properties of high energy density (HED) matter through hydrodynamics, solid-state hydrodynamics at high pressures, new hydrodynamic

  7. Nuclear Materials Technology Division/Los Alamos National Laboratory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    The Actinide Research Plutonium's dual roles as a nuclear fuel and as a weap- ons material ... the mechanical behavior of plutonium. 2 Nuclear Materials Technology DivisionLos Alamos ...

  8. Nuclear Materials Technology/Los Alamos National Laboratory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Focus on Students: 6 Students are Vital to the Lab 8 Nuclear Engineer Steven Alferink 10 ... has mobi- lized a strong effort in the Nuclear Materials Technology (NMT) and Materials ...

  9. Manual for Control And Accountability of Nuclear Materials

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1999-08-11

    DOE M 474.1-1 prescribes Department of Energy (DOE) requirements and procedures for nuclear material control and accountability (MC&A). This Manual supplements DOE O 474.1, Control and Accountability of Nuclear Materials.

  10. GTRI: Removing Vulnerable Civilian Nuclear and Radiological Material |

    National Nuclear Security Administration (NNSA)

    National Nuclear Security Administration Removing Vulnerable Civilian Nuclear and Radiological Material | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets

  11. Insider Threat to Nuclear and Radiological Materials: Fact Sheet | National

    National Nuclear Security Administration (NNSA)

    Nuclear Security Administration Insider Threat to Nuclear and Radiological Materials: Fact Sheet | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets

  12. Preventing Proliferation of Nuclear Materials and Technology | National

    National Nuclear Security Administration (NNSA)

    Nuclear Security Administration Preventing Proliferation of Nuclear Materials and Technology | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters

  13. Research Areas | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    (condensed matter physics and materials science, hydrodynamics and fluid dynamics). ... Hydrodynamic experiments in low energy density physics, high-temperature-pressure and rate ...

  14. Research Areas | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    National Laser User Facilities Program / Research Areas Research Areas National Laser Users' Facility Grant Program Research Areas The research tools and resources of the Omega Laser Facility, and the Laboratory for Laser Energetics, are available to National Laser Users' Facilities (NLUF) scientists for state-of-the-art basic research experiments in laser-matter interaction and related diagnostics. This includes, but is not limited to, inertial fusion, high energy density physics, plasma

  15. Research Areas | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    National Laser Users' Facility Grant Program / Research Areas Research Areas National Laser Users' Facility Grant Program Research Areas The research tools and resources of the Omega Laser Facility, and the Laboratory for Laser Energetics, are available to National Laser Users' Facilities (NLUF) scientists for state-of-the-art basic research experiments in laser-matter interaction and related diagnostics. This includes, but is not limited to, inertial fusion, high energy density physics, plasma

  16. USED NUCLEAR MATERIALS AT SAVANNAH RIVER SITE: ASSET OR WASTE?

    SciTech Connect (OSTI)

    Magoulas, V.

    2013-06-03

    The nuclear industry, both in the commercial and the government sectors, has generated large quantities of material that span the spectrum of usefulness, from highly valuable (assets) to worthless (wastes). In many cases, the decision parameters are clear. Transuranic waste and high level waste, for example, have no value, and is either in a final disposition path today, or in the case of high level waste awaiting a policy decision about final disposition. Other materials, though discardable, have intrinsic scientific or market value that may be hidden by the complexity, hazard, or cost of recovery. An informed decision process should acknowledge the asset value, or lack of value, of the complete inventory of materials, and the structure necessary to implement the range of possible options. It is important that informed decisions are made about the asset value for the variety of nuclear materials available. For example, there is a significant quantity of spent fuel available for recycle (an estimated $4 billion value in the Savannah River Sites (SRS) L area alone); in fact, SRS has already blended down more than 300 metric tons of uranium for commercial reactor use. Over 34 metric tons of surplus plutonium is also on a path to be used as commercial fuel. There are other radiological materials that are routinely handled at the site in large quantities that should be viewed as strategically important and / or commercially viable. In some cases, these materials are irreplaceable domestically, and failure to consider their recovery could jeopardize our technological leadership or national defense. The inventories of nuclear materials at SRS that have been characterized as waste include isotopes of plutonium, uranium, americium, and helium. Although planning has been performed to establish the technical and regulatory bases for their discard and disposal, recovery of these materials is both economically attractive and in the national interest.

  17. Scanning of vehicles for nuclear materials

    SciTech Connect (OSTI)

    Katz, J. I.

    2014-05-09

    Might a nuclear-armed terrorist group or state use ordinary commerce to deliver a nuclear weapon by smuggling it in a cargo container or vehicle? This delivery method would be the only one available to a sub-state actor, and it might enable a state to make an unattributed attack. Detection of a weapon or fissile material smuggled in this manner is difficult because of the large volume and mass available for shielding. Here I review methods for screening cargo containers to detect the possible presence of nuclear threats. Because of the large volume of innocent international commerce, and the cost and disruption of secondary screening by opening and inspection, it is essential that the method be rapid and have a low false-positive rate. Shielding can prevent the detection of neutrons emitted spontaneously or by induced fission. The two promising methods are muon tomography and high energy X-radiography. If they do not detect a shielded threat object they can detect the shield itself.

  18. NNSA recognizes Knight's service to Nuclear Materials Management Team |

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Y-12 National Security Complex NNSA recognizes ... NNSA recognizes Knight's service to Nuclear Materials Management Team Posted: August 13, 2015 - 3:38pm Print version Teresa Knight was honored by NNSA for her outstanding service to the Nuclear Materials Management The National Nuclear Security Administration presented CNS employee Teresa Knight with a special award in recognition of her outstanding service to the Department of Energy's Nuclear Materials Management Team. Knight began

  19. Nuclear Safety Specialist FTCP Functional Area Qualification Standards - Draft

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    83-20XX DOE-STD-1183-20XX Draft: Month Year DOE STANDARD NUCLEAR SAFETY SPECIALIST FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A: Approved for public release; distribution is unlimited NOT MEASUREMENT SENSITIVE DOE-STD-1183-20XX ii This document is available on the Department of Energy Technical Standards Program Website at

  20. Nuclear Explosive Safety Study Functional Area Qualification Standard

    Energy Savers [EERE]

    i NOT MEASUREMENT SENSITIVE DOE-STD-1185-2007 CHANGE NOTICE No.1 April 2010 DOE STANDARD NUCLEAR EXPLOSIVE SAFETY STUDY FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1185-2007 ii This document is available on the Department of Energy Technical Standards Program Web Site at

  1. Nuclear Explosives Safety Study Functional Area Qualification Standard

    Energy Savers [EERE]

    85-2007 September 2007 DOE STANDARD NUCLEAR EXPLOSIVE SAFETY STUDY FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DRAFT DOE-STD-1185-2007 ii This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DRAFT DOE-STD-1185-2007 iv

  2. Wide Area Thermal Processing of Light Emitting Materials

    SciTech Connect (OSTI)

    Duty, Chad E; Joshi, Pooran C; Jellison Jr, Gerald Earle; Angelini, Joseph Attilio; Sabau, Adrian S

    2011-10-01

    Laboratory laser materials synthesis of wide bandgap materials has been successfully used to create white light emitting materials (LEMs). This technology development has progressed to the exploration on design and construction of apparatus for wide area doping and phase transformation of wide bandgap material substrates. The objective of this proposal is to develop concepts for wide area doping and phase transformation based on AppliCote Associates, LLC laser technology and ORNL high density pulsed plasma arc technology.

  3. weapons material | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency...

  4. Nuclear Materials Characterization in the Materials and Fuels Complex Analytical Hot Cells

    SciTech Connect (OSTI)

    Michael Rodriquez

    2009-03-01

    As energy prices skyrocket and interest in alternative, clean energy sources builds, interest in nuclear energy has increased. This increased interest in nuclear energy has been termed the Nuclear Renaissance. The performance of nuclear fuels, fuels and reactor materials and waste products are becoming a more important issue as the potential for designing new nuclear reactors is more immediate. The Idaho National Laboratory (INL) Materials and Fuels Complex (MFC) Analytical Laboratory Hot Cells (ALHC) are rising to the challenge of characterizing new reactor materials, byproducts and performance. The ALHC is a facility located near Idaho Falls, Idaho at the INL Site. It was built in 1958 as part of the former Argonne National Laboratory West Complex to support the operation of the second Experimental Breeder Reactor (EBR-II). It is part of a larger analytical laboratory structure that includes wet chemistry, instrumentation and radiochemistry laboratories. The purpose of the ALHC is to perform analytical chemistry work on highly radioactive materials. The primary work in the ALHC has traditionally been dissolution of nuclear materials so that less radioactive subsamples (aliquots) could be transferred to other sections of the laboratory for analysis. Over the last 50 years though, the capabilities within the ALHC have also become independent of other laboratory sections in a number of ways. While dissolution, digestion and subdividing samples are still a vitally important role, the ALHC has stand alone capabilities in the area of immersion density, gamma scanning and combustion gas analysis. Recent use of the ALHC for immersion density shows that extremely fine and delicate operations can be performed with the master-slave manipulators by qualified operators. Twenty milligram samples were tested for immersion density to determine the expansion of uranium dioxide after irradiation in a nuclear reactor. The data collected confirmed modeling analysis with very tight precision. The gamma scanning equipment in the ALHC has taken on a new role also as a micro-gamma scanning system and has been put into service; allowing the linear and radial counting of a spent fuel segment to determine reaction characteristics within a small section of nuclear fuel. The nitrogen, oxygen and carbon analysis allows the identification of these impurities in spent nuclear fuel and also most oxides, nitrides, carbides, C-14 and tritium.

  5. Y-12 Removes Nuclear Materials from Two Facilities to Reduce Site's Nuclear

    National Nuclear Security Administration (NNSA)

    Footprint (Alpha 5 and 9720-38 No Longer Designated as Nuclear Facilities) | National Nuclear Security Administration Removes Nuclear Materials from Two Facilities to Reduce Site's Nuclear Footprint (Alpha 5 and 9720-38 No Longer Designated as Nuclear Facilities) | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering

  6. Nuclear Materials Technology Division/Los Alamos National Laboratory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ... 12 NewsMakers continued on page 10 2 Nuclear Materials Technology DivisionLos Alamos ... After extensive public debate resulted in the Nuclear Waste Policy Act of 1982, there have ...

  7. Regional Nuclear Workforce Development in the Central Savannah River Area

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Nuclear Workforce Development in the Central Savannah River Area Dr. Susan A. Winsor Aiken Technical College President: P.O. Box 696, Aiken, SC 29802, winsors@atc.edu Mindy Mets Nuclear Workforce Initiative Program Manager, SRS Community Reuse Organization: P.O. Box 696, Aiken, SC 29802, mindy.mets@srscro.org INTRODUCTION An expanding role for nuclear energy in the United States has dramatic implications for the nuclear workforce demand in the two-state region of Georgia and South Carolina known

  8. Nuclear Materials Management and Safeguards System Reporting and Data Submission

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1998-02-10

    The manual provides clear and detailed instructions and procedures for documenting and reporting data submissions for nuclear materials transactions, inventories, and material balances to the Nuclear Materials Management and Safeguards System (NMMSS). Cancels DOE 5633.3B. Canceled by DOE M 474.1-2A.

  9. Revisiting Statistical Aspects of Nuclear Material Accounting

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Burr, T.; Hamada, M. S.

    2013-01-01

    Nuclear material accounting (NMA) is the only safeguards system whose benefits are routinely quantified. Process monitoring (PM) is another safeguards system that is increasingly used, and one challenge is how to quantify its benefit. This paper considers PM in the role of enabling frequent NMA, which is referred to as near-real-time accounting (NRTA). We quantify NRTA benefits using period-driven and data-driven testing. Period-driven testing makes a decision to alarm or not at fixed periods. Data-driven testing decides as the data arrives whether to alarm or continue testing. The difference between period-driven and datad-riven viewpoints is illustrated by using one-year andmore » two-year periods. For both one-year and two-year periods, period-driven NMA using once-per-year cumulative material unaccounted for (CUMUF) testing is compared to more frequent Shewhart and joint sequential cusum testing using either MUF or standardized, independently transformed MUF (SITMUF) data. We show that the data-driven viewpoint is appropriate for NRTA and that it can be used to compare safeguards effectiveness. In addition to providing period-driven and data-driven viewpoints, new features include assessing the impact of uncertainty in the estimated covariance matrix of the MUF sequence and the impact of both random and systematic measurement errors.« less

  10. Absolute nuclear material assay using count distribution (LAMBDA) space

    DOE Patents [OSTI]

    Prasad, Manoj K.; Snyderman, Neal J.; Rowland, Mark S.

    2012-06-05

    A method of absolute nuclear material assay of an unknown source comprising counting neutrons from the unknown source and providing an absolute nuclear material assay utilizing a model to optimally compare to the measured count distributions. In one embodiment, the step of providing an absolute nuclear material assay comprises utilizing a random sampling of analytically computed fission chain distributions to generate a continuous time-evolving sequence of event-counts by spreading the fission chain distribution in time.

  11. Absolute nuclear material assay using count distribution (LAMBDA) space

    DOE Patents [OSTI]

    Prasad, Manoj K.; Snyderman, Neal J.; Rowland, Mark S.

    2015-12-01

    A method of absolute nuclear material assay of an unknown source comprising counting neutrons from the unknown source and providing an absolute nuclear material assay utilizing a model to optimally compare to the measured count distributions. In one embodiment, the step of providing an absolute nuclear material assay comprises utilizing a random sampling of analytically computed fission chain distributions to generate a continuous time-evolving sequence of event-counts by spreading the fission chain distribution in time.

  12. Cleanup Contractor Achieves ‘Elite’ Nuclear Material Accountability Status

    Broader source: Energy.gov [DOE]

    PADUCAH, Ky. – EM’s cleanup contractor at the Paducah site has received national acclaim for timeliness of reporting and promptness in reconciling nuclear material inventories.

  13. Microsoft PowerPoint - Programmatic Update Nuclear Material...

    National Nuclear Security Administration (NNSA)

    nuclear material issues The path of continuous improvement is dependent on sharing and disseminating lessons learned and experiences - Your active engagement is critical. 6...

  14. Nuclear Material Recovery | Y-12 National Security Complex

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    - energy. Global Security Cooley joins Y-12's Global Security and Strategic Partnerships Manufacturing and Technical Services Nuclear Material Recovery Central Scrap Management...

  15. Control and Accountability of Nuclear Materials: Responsibilities and Authorities

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1992-09-23

    The order prescribes the Department of Energy (DOE) policies, responsibilities, and authorities for control and accountability of nuclear materials. Cancels DOE O 5633.2.

  16. Audit of Internal Controls Over Special Nuclear Materials, IG...

    Energy Savers [EERE]

    0388 "Audit of Internal Controls Over Special Nuclear Materials" This report is not available electronically. However, copies may be obtained by calling the Office of Inspector...

  17. Office of Nuclear Material Integration (ONMI), NA-73

    National Nuclear Security Administration (NNSA)

    Energy Agency (IAEA) under International Safeguards Agreements Nuclear Materials Financial M anagement (Asset Tracking for CFO) Critical Support of Regulatory Functions ...

  18. Neutron Detectors for Detection of Nuclear Materials at LANL...

    Office of Science (SC) Website

    The applications are in (a) detection of smuggled neutron-emitting special nuclear materials (SNM), such as weapons grade plutonium and certain uranium compounds, (b) terrorist ...

  19. Nuclear Materials Management & Safeguards System | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration Management & Safeguards System | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery Jobs

  20. Material Management and Minimization | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    Management and Minimization | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering...

  1. Material Control & Accountability | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration Control & Accountability | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery Jobs Apply for Our

  2. Office of Material Consolidation & Civilian Sites | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration Material Consolidation & Civilian Sites | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo

  3. NNSA Recovers Radiological Material from Mexico | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration Recovers Radiological Material from Mexico | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery Jobs

  4. Office of Weapons Material Protection | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration Weapons Material Protection | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery Jobs Apply for Our

  5. Offsite environmental monitoring report. Radiation monitoring around United States nuclear test areas, calendar year 1982

    SciTech Connect (OSTI)

    Black, S. C.; Grossman, R. F.; Mullen, A. A.; Potter, G. D.; Smith, D. D.

    1983-07-01

    A principal activity of the Offsite Radiological Safety Program is routine environmental monitoring for radioactive materials in various media and for radiation in areas which may be affected by nuclear tests. It is conducted to document compliance with standards, to identify trends, and to provide information to the public. This report summarizes these activities for CY 1982.

  6. Novel Approach to Plasma Facing Materials in Nuclear Fusion Reactors

    SciTech Connect (OSTI)

    Livramento, V.; Correia, J. B.; Shohoji, N.; Osawa, E.; Nunes, D.

    2008-04-07

    A novel material design in nuclear fusion reactors is proposed based on W-nDiamond nanostructured composites. Generally, a microstructure refined to the nanometer scale improves the mechanical strength due to modification of plasticity mechanisms. Moreover, highly specific grain-boundary area raises the number of sites for annihilation of radiation induced defects. However, the low thermal stability of fine-grained and nanostructured materials demands the presence of particles at the grain boundaries that can delay coarsening by a pinning effect. As a result, the concept of a composite is promising in the field of nanostructured materials. The hardness of diamond renders nanodiamond dispersions excellent reinforcing and stabilization candidates and, in addition, diamond has extremely high thermal conductivity. Consequently, W-nDiamond nanocomposites are promising candidates for thermally stable first-wall materials. The proposed design involves the production of W/W-nDiamond/W-Cu/Cu layered castellations. The W, W-nDiamond and W-Cu layers are produced by mechanical alloying followed by a consolidation route that combines hot rolling with spark plasma sintering (SPS). Layer welding is achieved by spark plasma sintering. The present work describes the mechanical alloying processsing and consolidation route used to produce W-nDiamond composites, as well as microstructural features and mechanical properties of the material produced Long term plasma exposure experiments are planned at ISTTOK and at FTU (Frascati)

  7. Material Disposition | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Disposition | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery Jobs Apply for Our Jobs Our Jobs Working at NNSA Blog

  8. material protection | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    protection | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery Jobs Apply for Our Jobs Our Jobs Working at NNSA Blog

  9. material recovery | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    recovery | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery Jobs Apply for Our Jobs Our Jobs Working at NNSA Blog Home

  10. material removal | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    removal | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery Jobs Apply for Our Jobs Our Jobs Working at NNSA Blog Home

  11. material consolidation | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    consolidation | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery Jobs Apply for Our Jobs Our Jobs Working at NNSA Blog

  12. NNSA: Securing Domestic Radioactive Material | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration Mission In 2004 NNSA established the Global Threat Reduction Initiative (GTRI) in the Office of Defense Nuclear Nonproliferation to, as quickly as possible, identify, secure, remove and/or facilitate the disposition of high risk nuclear and radiological materials around the world that pose a threat to the United States and the international community. GTRI's mission is to reduce and protect vulnerable nuclear and radiological material located at civilian sites worldwide. GTRI

  13. Office of Nuclear Material Integration (ONMI), NA-73

    National Nuclear Security Administration (NNSA)

    Office of Nuclear Material Integration (ONMI), NA-73 Over 420 Government & Commercial Nuclear Entities currently report to NMMSS Mission U.S. Government's Official Database to Track Transactions, Movements and Inventories of Nuclear Materials throughout the U.S. as well as Imports and Exports Jointly funded by the NRC & NNSA - Managed by NA-73 Fuel Cycle Facilities  Conversion  Enrichment  Fuel Fabrication  Power Reactors, etc. DOE/NNSA  Defense Programs  Naval

  14. Anomalies in Proposed Regulations for the Release of Redundant Material from Nuclear and Non-nuclear Industries

    SciTech Connect (OSTI)

    Menon, S.

    2002-02-26

    Now that increasing numbers of nuclear power stations are reaching the end of their commercially useful lives, the management of the large quantities of very low level radioactive material that arises during their decommissioning has become a major subject of discussion, with very significant economic implications. Much of this material can, in an environmentally advantageous manner, be recycled for reuse without radiological restrictions. Much larger quantities--2-3 orders of magnitude larger--of material, radiologically similar to the candidate material for recycling from the nuclear industry, arise in non-nuclear industries like coal, fertilizer, oil and gas, mining, etc. In such industries, naturally occurring radioactivity is artificially concentrated in products, by-products or waste to form TENORM (Technologically Enhanced Naturally Occurring Radioactive Material). It is only in the last decade that the international community has become aware of the prevalence of T ENORM, specially the activity levels and quantities arising in so many nonnuclear industries. The first reaction of international organizations seems to have been to propose ''double'' standards for the nuclear and non-nuclear industries, with very stringent release criteria for radioactive material from the regulated nuclear industry and up to a hundred times more liberal criteria for the release/exemption of TENORM from the as yet unregulated non-nuclear industries. There are, however, many significant strategic issues that need to be discussed and resolved. An interesting development, for both the nuclear and non-nuclear industries, is the increased scientific scrutiny that the populations of naturally high background dose level areas of the world are being subject to. Preliminary biological studies have indicated that the inhabitants of such areas, exposed to many times the permitted occupational doses for nuclear workers, have not shown any differences in cancer mortality, life expectancy, chromosome aberrations or immune function, in comparison with those living in normal background areas. The paper discusses these and other strategic issues regarding the management of nuclear and non-nuclear radioactive material, underlining the need for consistency in regulatory treatment.

  15. fissile material | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy ... (DOE) announced plans to reduce the proliferation threat from stockpiles of surplus ...

  16. Next Generation Nuclear Plant Materials Research and Development Program Plan

    SciTech Connect (OSTI)

    G.O. Hayner; R.L. Bratton; R.N. Wright

    2005-09-01

    The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years. The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Project is envisioned to demonstrate the following: (1) A full-scale prototype VHTR by about 2021; (2) High-temperature Brayton Cycle electric power production at full scale with a focus on economic performance; (3) Nuclear-assisted production of hydrogen (with about 10% of the heat) with a focus on economic performance; and (4) By test, the exceptional safety capabilities of the advanced gas-cooled reactors. Further, the NGNP program will: (1) Obtain a Nuclear Regulatory Commission (NRC) License to construct and operate the NGNP, this process will provide a basis for future performance based, risk-informed licensing; and (2) Support the development, testing, and prototyping of hydrogen infrastructures. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. The NGNP Materials R&D Program includes the following elements: (1) Developing a specific approach, program plan and other project management tools for managing the R&D program elements; (2) Developing a specific work package for the R&D activities to be performed during each government fiscal year; (3) Reporting the status and progress of the work based on committed deliverables and milestones; (4) Developing collaboration in areas of materials R&D of benefit to the NGNP with countries that are a part of the Generation IV International Forum; and (5) Ensuring that the R&D work performed in support of the materials program is in conformance with established Quality Assurance and procurement requirements. The objective of the NGNP Materials R&D Program is to provide the essential materials R&D needed to support the design and licensing of the reactor and balance of plant, excluding the hydrogen plant. The materials R&D program is being initiated prior to the design effort to ensure that materials R&D activities are initiated early enough to support the design process and support the Project Integrator. The thermal, environmental, and service life conditions of the NGNP will make selection and qualification of some high-temperature materials a significant challenge; thus, new materials and approaches may be required.

  17. weapons material protection | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Sheets Newsletters Press Releases Video Gallery Photo Gallery Jobs Apply for Our Jobs Our Jobs Working at NNSA Blog Home weapons material protection weapons material protection...

  18. R&D for Better Nuclear Security: Radiation Detector Materials

    SciTech Connect (OSTI)

    Kammeraad, J E

    2009-04-02

    I am going to talk about the need for better materials for radiation detectors. I believe that government investment in this area can enable transformational technology change that could impact domestic nuclear security and also national nuclear security in some very positive and powerful ways. I'm not going to give you a lecture on how radiation detectors work, but I am going to tell you a bit about today's off-the-shelf technology and why it is not sufficient, what we need, and what security benefit you could get from improvements. I think we're at a critical point in time for some very impactful investments. In particular I'm going to focus on the use of gamma-ray radiation detectors at ports of entry. Not long before DHS was formed, Congress decreed that counter measures against the delivery of radiological and nuclear threats would be put in place at US ports of entry, under the authority of US Customs (later Customs and Border Protection in DHS). This included the screening of all cars and trucks passing through a port of entry. Existing off-the-shelf radiation detectors had to be selected for this purpose. Plans were made to make the most of the available technologies, but there are some inherent limitations of these detectors, plus the operational setting can bring out other limitations.

  19. Metal-organic framework materials with ultrahigh surface areas

    DOE Patents [OSTI]

    Farha, Omar K.; Hupp, Joseph T.; Wilmer, Christopher E.; Eryazici, Ibrahim; Snurr, Randall Q.; Gomez-Gualdron, Diego A.; Borah, Bhaskarjyoti

    2015-12-22

    A metal organic framework (MOF) material including a Brunauer-Emmett-Teller (BET) surface area greater than 7,010 m.sup.2/g. Also a metal organic framework (MOF) material including hexa-carboxylated linkers including alkyne bond. Also a metal organic framework (MOF) material including three types of cuboctahedron cages fused to provide continuous channels. Also a method of making a metal organic framework (MOF) material including saponifying hexaester precursors having alkyne bonds to form a plurality of hexa-carboxylated linkers including alkyne bonds and performing a solvothermal reaction with the plurality of hexa-carboxylated linkers and one or more metal containing compounds to form the MOF material.

  20. Public perception of the nuclear area in Brazil

    SciTech Connect (OSTI)

    Imeida, R.A. de

    2013-07-01

    In Brazil electricity production is proving increasingly important, the Brazilian government has recently launched the National Energy Plan, PNE-2030 which aims, among other objectives, to conclude construction of the Angra 3 plant and to deploy new nuclear power plants in the Northeast region. The Brazilian government wants to assess how the public has perceived its energy policy and what the public thinks about the nuclear issue. A public opinion survey was performed and sampling resulted in 127 respondents who were stratified by gender, age and educational level. The survey results show that although most respondents have post-graduate degrees, 64.6% are not aware of, or had never heard of PNE-2030. While 72 respondents consider nuclear energy as an alternative source of clean energy, 84 respondents did not know where the next Brazilian nuclear power plant will be built. The nuclear regulator, CNEN, is seen by 45.7% of respondents as the body that has most credibility to talk about the safety of nuclear power plants and the media most used to obtain information about the nuclear area were newspapers and discussion forums, with 52 and 50 votes respectively. These results prove the need to implement communication plans with clear and concise goals for different segments of society, since the degree of understanding differs within each segment.

  1. A systematic method for identifying vital areas at complex nuclear facilities.

    SciTech Connect (OSTI)

    Beck, David Franklin; Hockert, John

    2005-05-01

    Identifying the areas to be protected is an important part of the development of measures for physical protection against sabotage at complex nuclear facilities. In June 1999, the International Atomic Energy Agency published INFCIRC/225/Rev.4, 'The Physical Protection of Nuclear Material and Nuclear Facilities.' This guidance recommends that 'Safety specialists, in close cooperation with physical protection specialists, should evaluate the consequences of malevolent acts, considered in the context of the State's design basis threat, to identify nuclear material, or the minimum complement of equipment, systems or devices to be protected against sabotage.' This report presents a structured, transparent approach for identifying the areas that contain this minimum complement of equipment, systems, and devices to be protected against sabotage that is applicable to complex nuclear facilities. The method builds upon safety analyses to develop sabotage fault trees that reflect sabotage scenarios that could cause unacceptable radiological consequences. The sabotage actions represented in the fault trees are linked to the areas from which they can be accomplished. The fault tree is then transformed (by negation) into its dual, the protection location tree, which reflects the sabotage actions that must be prevented in order to prevent unacceptable radiological consequences. The minimum path sets of this fault tree dual yield, through the area linkage, sets of areas, each of which contains nuclear material, or a minimum complement of equipment, systems or devices that, if protected, will prevent sabotage. This method also provides guidance for the selection of the minimum path set that permits optimization of the trade-offs among physical protection effectiveness, safety impact, cost and operational impact.

  2. Nuclear Energy Advisory Committee Meeting Materials | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Virginia July 30, 1999 Meeting Materials: July 29-30, 1999 NEAC Meeting Embassy Suites Hotel Arlington, Virginia November 18, 1998 Meeting Materials: Nov 17-18, 1998 NEAC Meeting...

  3. Cleanup Contractor Achieves 'Elite' Nuclear Material Accountability...

    Broader source: Energy.gov (indexed) [DOE]

    ... They are being stored at the site for future recovery of UF6 material during plant decommissioning when systems are in place to remove the material safely and economically. LATA ...

  4. Global Material Security | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Global Material Security Global Material Security NNSA Provides Tajikistan Specialized Vehicles to Transport Radiological Materials NNSA Program Manager Nick Cavellero, right, and NRSA Director of the Department of Information and International Relations Ilkhom Mirsaidov, left, with two specialized vehicles purchased by NNSA for

  5. SRS K-AREA MATERIAL STORAGE - EXPANDING CAPABILITIES

    SciTech Connect (OSTI)

    Koenig, R.

    2013-07-02

    In support of the Department of Energys continued plans to de-inventory and reduce the footprint of Cold War era weapons material production sites, the K-Area Material Storage (KAMS) facility, located in the K-Area Complex (KAC) at the Savannah River Site reservation, has expanded since its startup authorization in 2000 to accommodate DOEs material consolidation mission. During the facilitys growth and expansion, KAMS will have expanded its authorization capability of material types and storage containers to allow up to 8200 total shipping containers once the current expansion effort completes in 2014. Recognizing the need to safely and cost effectively manage other surplus material across the DOE Complex, KAC is constantly evaluating the storage of different material types within K area. When modifying storage areas in KAC, the Documented Safety Analysis (DSA) must undergo extensive calculations and reviews; however, without an extensive and proven security posture the possibility for expansion would not be possible. The KAC maintains the strictest adherence to safety and security requirements for all the SNM it handles. Disciplined Conduct of Operations and Conduct of Projects are demonstrated throughout this historical overview highlighting various improvements in capability, capacity, demonstrated cost effectiveness and utilization of the KAC as the DOE Center of Excellence for safe and secure storage of surplus SNM.

  6. System for detecting special nuclear materials

    DOE Patents [OSTI]

    Jandel, Marian; Rusev, Gencho Yordanov; Taddeucci, Terry Nicholas

    2015-07-14

    The present disclosure includes a radiological material detector having a convertor material that emits one or more photons in response to a capture of a neutron emitted by a radiological material; a photon detector arranged around the convertor material and that produces an electrical signal in response to a receipt of a photon; and a processor connected to the photon detector, the processor configured to determine the presence of a radiological material in response to a predetermined signature of the electrical signal produced at the photon detector. One or more detectors described herein can be integrated into a detection system that is suited for use in port monitoring, treaty compliance, and radiological material management activities.

  7. Office of Global Material Security | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration Global Material Security | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery Jobs Apply for Our Jobs

  8. Highly Enriched Uranium Materials Facility | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration Materials Facility | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery Jobs Apply for Our Jobs Our

  9. Real-Time Characterization of Special Nuclear Materials

    SciTech Connect (OSTI)

    Walston, Sean; Candy, Jim; Chambers, Dave; Chandrasekaran, Hema; Snyderman, Neal

    2015-09-04

    When confronting an item that may contain nuclear material, it is urgently necessary to determine its characteristics. Our goal is to provide accurate information with high-con dence as rapidly as possible.

  10. NNSA recognizes Knight's service to Nuclear Materials Management...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Management Team. Knight began co-chairing the team in 2005 when the NMMT was in its infancy. The team of NNSA federal and contractor nuclear material managers develops...

  11. Manual for Control and Accountability of Nuclear Materials

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2003-06-13

    The manual prescribes requirements and assign responsibilities for nuclear material control and accountability. Cancels DOE M 474.1-1A. Canceled by DOE M 470.4-6.

  12. Control and Accountability of Nuclear Materials Responsibilities and Authorities

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1988-01-29

    The order prescribe the Department of Energy (DOE) policies, responsibilities, and authorities for control and accountability of nuclear materials. Cancels DOE O 5630.1. Canceled by DOE O 5633.2A.

  13. Manual for Control and Accountability of Nuclear Materials

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2000-11-22

    The manual prescribes requirements and procedures for nuclear material control and accountability (MC&A). Cancels DOE M 474.1-1. Canceled by DOE M 474.1-1B.

  14. Energy Frontier Research Center Center for Materials Science of Nuclear

    Office of Scientific and Technical Information (OSTI)

    Fuels (Technical Report) | SciTech Connect Frontier Research Center Center for Materials Science of Nuclear Fuels Citation Details In-Document Search Title: Energy Frontier Research Center Center for Materials Science of Nuclear Fuels Scientific Successes * The first phonon density of states (PDOS) measurements for UO2 to include anharmonicity were obtained using time-of-flight inelastic neutron scattering at the Spallation Neutron Source (SNS), and an innovative, experimental-based

  15. Energy Frontier Research Center Center for Materials Science of Nuclear

    Office of Scientific and Technical Information (OSTI)

    Fuels (Technical Report) | SciTech Connect Technical Report: Energy Frontier Research Center Center for Materials Science of Nuclear Fuels Citation Details In-Document Search Title: Energy Frontier Research Center Center for Materials Science of Nuclear Fuels × You are accessing a document from the Department of Energy's (DOE) SciTech Connect. This site is a product of DOE's Office of Scientific and Technical Information (OSTI) and is provided as a public service. Visit OSTI to utilize

  16. Characterization of ion-induced radiation effects in nuclear materials

    Office of Scientific and Technical Information (OSTI)

    using synchrotron x-ray techniques (Journal Article) | SciTech Connect Characterization of ion-induced radiation effects in nuclear materials using synchrotron x-ray techniques Citation Details In-Document Search Title: Characterization of ion-induced radiation effects in nuclear materials using synchrotron x-ray techniques Authors: Lang, Maik ; Tracy, Cameron L. ; Palomares, Raul I. ; Zhang, Fuxiang ; Severin, Daniel ; Bender, Markus ; Trautmann, Christina ; Park, Changyong ; Prakapenka,

  17. Energy Frontier Research Center Center for Materials Science of Nuclear

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Fuels (Technical Report) | SciTech Connect Technical Report: Energy Frontier Research Center Center for Materials Science of Nuclear Fuels Citation Details In-Document Search Title: Energy Frontier Research Center Center for Materials Science of Nuclear Fuels Scientific Successes * The first phonon density of states (PDOS) measurements for UO2 to include anharmonicity were obtained using time-of-flight inelastic neutron scattering at the Spallation Neutron Source (SNS), and an innovative,

  18. Nuclear reference materials to meet the changing needs of the global nuclear community

    SciTech Connect (OSTI)

    Martin, H.R.; Gradle, C.G.; Narayanan, U.I.; Oldham, R.D.; Mitchell, W.G.

    1995-12-31

    New Brunswick Laboratory (NBL) serves as the US Government`s Certifying Authority for nuclear reference materials and measurement calibration standards. In this role, NBL provides nuclear reference materials certified for chemical and/or isotopic compositions traceable to a nationally accepted, internationally compatible reference base. Emphasis is now changing as to the types of traceable nuclear reference materials needed as operations change within the Department of Energy (DOE) complex and at nuclear facilities around the world. Environmental and waste minimization issues, facilities and materials transitioning from processing to storage modes with corresponding changes in the types of measurements being performed, emphasis on requirements for characterization of waste materials, difficulties in transporting nuclear materials, and International factors, including International Atomic Energy Agency (IAEA) inspection of excess US nuclear materials, are all contributing influences. During these changing times, ft is critical that traceable reference materials be provided for calibration or validation of the performance of measurement systems. This paper will describe actions taken and planned to meet the changing reference material needs of the global nuclear community.

  19. Detecting fission from special nuclear material sources

    DOE Patents [OSTI]

    Rowland, Mark S. (Alamo, CA); Snyderman, Neal J. (Berkeley, CA)

    2012-06-05

    A neutron detector system for discriminating fissile material from non-fissile material wherein a digital data acquisition unit collects data at high rate, and in real-time processes large volumes of data directly into information that a first responder can use to discriminate materials. The system comprises counting neutrons from the unknown source and detecting excess grouped neutrons to identify fission in the unknown source. The system includes a graphing component that displays the plot of the neutron distribution from the unknown source over a Poisson distribution and a plot of neutrons due to background or environmental sources. The system further includes a known neutron source placed in proximity to the unknown source to actively interrogate the unknown source in order to accentuate differences in neutron emission from the unknown source from Poisson distributions and/or environmental sources.

  20. Nuclear forensics of special nuclear material at Los Alamos: three recent studies

    SciTech Connect (OSTI)

    Tandon, Lav; Gallimore, David L; Garduon, Katherine; Keller, Russell C; Kuhn, Kevin J; Lujan, Elmer J; Martinez, Alexander; Myers, Steven C; Moore, Steve S; Porterfield, Donivan R; Schwartz, Daniel S; Spencer, Khalil J; Townsend, Lisa E; Xu, Ning

    2010-01-01

    Nuclear forensics of special nuclear materials is a highly specialized field because there are few analytical laboratories in the world that can safely handle nuclear materials, perform high accuracy and precision analysis using validated analytical methods. The goal of nuclear forensics is to establish an unambiguous link between illicitly trafficked nuclear material and its origin. The Los Alamos National Laboratory Nuclear Materials Signatures Program has implemented a graded 'conduct of operations' type approach for determining the unique nuclear, chemical, and physical signatures needed to identify the manufacturing process, intended use, and origin of interdicted nuclear material. In our approach an analysis flow path was developed for determining key signatures necessary for attributing unknown materials to a source. This analysis flow path included both destructive (i.e., alpha spectrometry, ICP-MS, ICP-AES, TIMS, particle size distribution, density and particle fractionation) and non-destructive (i.e., gamma-ray spectrometry, optical microscopy, SEM, XRD, and x-ray fluorescence) characterization techniques. Analytical techniques and results from three recent cases characterized by this analysis flow path along with an evaluation of the usefulness of this approach will be discussed in this paper.

  1. First time nuclear material detection by one short-pulse-laser...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Technical Articles First time nuclear material detection by one short-pulse-laser-driven neutron source First time nuclear material detection by one short-pulse-laser-driven...

  2. SRS Completes Annual Examinations to Verify Safe Storage of Nuclear Materials

    Broader source: Energy.gov [DOE]

    AIKEN, S.C. – The EM program at the Savannah River Site (SRS) recently completed an annual process in K Area that validates the site’s ongoing commitment to maintaining the safety and security of nuclear materials stored there.

  3. Nuclear reference materials to meet the changing needs of the global nuclear community

    SciTech Connect (OSTI)

    Martin, H.R.; Gradle, C.G.; Narayanan, U.I.; Oldham, R.D.

    1995-12-31

    New Brunswick Laboratory (NBL) serves as the U.S. Government`s certifying authority for nuclear reference materials and measurement calibration standards. In this role, NBL provides nuclear reference materials certified for chemical and/or isotopic compositions traceable to a nationally accepted, internationally compatible reference base. Emphasis is now changing as to the types of traceable nuclear reference materials needed as operations change within the Department of Energy complex and at nuclear facilities around the world. New challenges include: environmental and waste minimization issues, facilities and materials transitioning from processing to storage modes with corresponding changes in the types of measurements being performed, emphasis on requirements for characterization of waste materials, and difficulties in transporting nuclear materials and international factors, including IAEA influences. During these changing times, it is critical that traceable reference materials be provided for calibration or validation of the performance of measurement systems. This paper will describe actions taken and planned to meet the changing reference material needs of the global nuclear community.

  4. Graphite matrix materials for nuclear waste isolation

    SciTech Connect (OSTI)

    Morgan, W.C.

    1981-06-01

    At low temperatures, graphites are chemically inert to all but the strongest oxidizing agents. The raw materials from which artificial graphites are produced are plentiful and inexpensive. Morover, the physical properties of artificial graphites can be varied over a very wide range by the choice of raw materials and manufacturing processes. Manufacturing processes are reviewed herein, with primary emphasis on those processes which might be used to produce a graphite matrix for the waste forms. The approach, recommended herein, involves the low-temperature compaction of a finely ground powder produced from graphitized petroleum coke. The resultant compacts should have fairly good strength, low permeability to both liquids and gases, and anisotropic physical properties. In particular, the anisotropy of the thermal expansion coefficients and the thermal conductivity should be advantageous for this application. With two possible exceptions, the graphite matrix appears to be superior to the metal alloy matrices which have been recommended in prior studies. The two possible exceptions are the requirements on strength and permeability; both requirements will be strongly influenced by the containment design, including the choice of materials and the waste form, of the multibarrier package. Various methods for increasing the strength, and for decreasing the permeability of the matrix, are reviewed and discussed in the sections in Incorporation of Other Materials and Elimination of Porosity. However, it would be premature to recommend a particular process until the overall multi-barrier design is better defined. It is recommended that increased emphasis be placed on further development of the low-temperature compacted graphite matrix concept.

  5. Rattling Nucleons: New Developments in Active Interrogation of Special Nuclear Material

    SciTech Connect (OSTI)

    Robert C. Runkle; David L. Chichester; Scott J. Thompson

    2012-01-01

    Active interrogation is a vigorous area of research and development due to its promise of offering detection and characterization capabilities of special nuclear material in environments where passive detection fails. The primary value added by active methods is the capability to penetrate shielding - special nuclear material itself, incidental materials, or intentional shielding - and advocates hope that active interrogation will provide a solution to the problem of detecting shielded uranium, which is at present the greatest obstacle to interdiction efforts. The technique also provides a unique benefit for quantifying nuclear material in high background-radiation environments, an area important for nuclear material safeguards and material accountancy. Progress has been made in the field of active interrogation on several fronts, most notably in the arenas of source development, systems integration, and the integration and exploitation of multiple fission and non-fission signatures. But penetration of interrogating radiation often comes at a cost, not only in terms of finance and dose but also in terms of induced backgrounds, system complexity, and extended measurement times (including set up and acquisition). These costs make the calculus for deciding to implement active interrogation more subtle than may be apparent. The purpose of this review is thus to examine existing interrogation methods, compare and contrast their attributes and limitations, and identify missions where active interrogation may hold the most promise.

  6. International training course on nuclear materials accountability for safeguards purposes

    SciTech Connect (OSTI)

    Not Available

    1980-12-01

    The two volumes of this report incorporate all lectures and presentations at the International Training Course on Nuclear Materials Accountability and Control for Safeguards Purposes, held May 27-June 6, 1980, at the Bishop's Lodge near Santa Fe, New Mexico. The course, authorized by the US Nuclear Non-Proliferation Act and sponsored by the US Department of Energy in cooperation with the International Atomic Energy Agency, was developed to provide practical training in the design, implementation, and operation of a National system of nuclear materials accountability and control that satisfies both National and IAEA International safeguards objectives. Volume I, covering the first week of the course, presents the background, requirements, and general features of material accounting and control in modern safeguard systems. Volume II, covering the second week of the course, provides more detailed information on measurement methods and instruments, practical experience at power reactor and research reactor facilities, and examples of operating state systems of accountability and control.

  7. Microsoft Word - Final Nuclear Materials Management and Safeguards System Users Guide 2 4-3-13.docx

    National Nuclear Security Administration (NNSA)

    Nuclear Materials Management and Safeguards Users Guide National Nuclear Security Administration Office of Nuclear Materials Integration Office of Nuclear Materials Integration Nuclear Materials Management and Safeguards System (NMMSS) Users Guide-Rev. 2.0 Prepared by: Department of Energy National Nuclear Security Administration Nuclear Materials Integration - NA-73 April 2013 Xavier Ascanio Office of Nuclear Materials Integration Nuclear Materials Management and 73 NMMSS User Guide 2.0 April

  8. Application of Telepresence Technologies to Nuclear Material Safeguards

    SciTech Connect (OSTI)

    Wright, M.C.; Rome, J.A.

    1999-09-20

    Implementation of remote monitoring systems has become a priority area for the International Atomic Energy Agency and other international inspection regimes. For the past three years, DOE2000 has been the US Department of Energy's (DOE's) initiative to develop innovative applications to exploit the capabilities of broadband networks and media integration. The aim is to enhance scientific collaboration by merging computing and communications technologies. These Internet-based telepresence technologies could be easily extended to provide remote monitoring and control for confidence building and transparency systems at nuclear facilities around the world. One of the original DOE2000 projects, the Materials Microcharacterization Collaboratory is an interactive virtual laboratory, linking seven DOE user facilities located across the US. At these facilities, external collaborators have access to scientists, data, and instrumentation, all of which are available to varying degrees using the Internet. Remote operation of the instruments varies between passive (observational) to active (direct control), in many cases requiring no software at the remote site beyond a Web browser. Live video streams are continuously available on the Web so that participants can see what is happening at a particular location. An X.509 certificate system provides strong authentication, The hardware and software are commercially available and are easily adaptable to safeguards applications.

  9. Nuclear Explosive Safety Study Functional Area Qualification Standard

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2010-05-27

    A Nuclear Explosive Safety Study (NESS) is performed on all DOE Nuclear Explosive Operations (NEOs) in accordance with DOE O 452.1D, Nuclear Explosive and Weapon Surety Program; DOE O 452.2D, Nuclear Explosive Safety; and DOE M 452.2-2, Nuclear Explosive Safety Evaluation Processes.

  10. Illicit Trafficking in Radiological and Nuclear Materials. Lack of Regulations and Attainable Disposal for Radioactive Materials Make Them More Vulnerable than Nuclear Materials

    SciTech Connect (OSTI)

    Balatsky, G.I.; Severe, W.R.; Leonard, L.

    2007-07-01

    Illicit trafficking in nuclear and radioactive materials is far from a new issue. Reports of nuclear materials offered for sale as well as mythical materials such as red mercury date back to the 1960's. While such reports were primarily scams, it illustrates the fact that from an early date there were criminal elements willing to sell nuclear materials, albeit mythical ones, to turn a quick profit. In that same time frame, information related to lost and abandoned radioactive sources began to be reported. Unlike reports on nuclear material of that era, these reports on abandoned sources were based in fact - occasionally associated with resulting injury and death. With the collapse of the Former Soviet Union, illicit trafficking turned from a relatively unnoticed issue to one of global concern. Reports of unsecured nuclear and radiological material in the states of the Former Soviet Union, along with actual seizures of such material in transit, gave the clear message that illicit trafficking was now a real and urgent problem. In 1995, the IAEA established an Illicit Trafficking Data Base to keep track of confirmed instances. Illicit Trafficking is deemed to include not only radioactive materials that have been offered for sale or crossed international boarders, but also such materials that are no longer under appropriate regulatory control. As an outcome of 9/11, the United States took a closer look at illicit nuclear trafficking as well as a reassessment of the safety and security of nuclear and other radioactive materials both in the United States and Globally. This reassessment launched heightened controls and security domestically and increased our efforts internationally to prevent illicit nuclear trafficking. This reassessment also brought about the Global Threat Reduction Initiative which aims to further reduce the threats of weapons usable nuclear materials as well those of radioactive sealed sources. This paper will focus on the issues related to a subset of the materials involved in illicit trafficking in nuclear and radioactive materials, that of radioactive sealed sources. The focus on radioactive sealed sources is based on our belief that insufficient attention has been paid to trafficking incidents involving such sources which constitute the majority of trafficking cases. According to the IAEA's Illicit Trafficking Data Base, as of December 31 2005 there were 827 confirmed cases reporting by the participating states, including 250 incidents (or 30%) involved nuclear and other radioactive materials and 566 (or 68%) involved other radioactive materials, mostly radioactive sources, and radioactively contaminated materials. Experts in the Lugar Survey on Proliferation Threat and Response (June 2005) agreed that an attack with a Radiological Dispersion Device (RDD) was the most probable form of nuclear terrorism the world could expect over the next decade. At the same time radiological materials are used in wide a variety of applications, located in virtually every country and in general, radiological materials are far easier to access than nuclear materials. It has become increasingly obvious that the lack of a cradle-to-grave approach for sealed radioactive sources that have reached the end of their useful life is the main reason that sources are abandoned. It appears that the questions will ultimately become whether industry will impose additional regulations upon itself and become self-regulating with respect to repatriating radioactive material at the end of service life, or whether national authorities at some point will take actions and regulate the industry. Argentina, which is one of the most advanced countries regarding control of radiological sources adopted additional measures to safeguard its radiological materials to a level comparable to that proscribed for nuclear materials. This approach, while highly successful, has led to some minor unforeseen consequences, namely insufficient funds to implement all regulations in full and a lack of inspectors and appropriate equipment to assure compliance This

  11. Chemical digestion of low level nuclear solid waste material

    DOE Patents [OSTI]

    Cooley, Carl R.; Lerch, Ronald E.

    1976-01-01

    A chemical digestion for treatment of low level combustible nuclear solid waste material is provided and comprises reacting the solid waste material with concentrated sulfuric acid at a temperature within the range of 230.degree.-300.degree.C and simultaneously and/or thereafter contacting the reacting mixture with concentrated nitric acid or nitrogen dioxide. In a special embodiment spent ion exchange resins are converted by this chemical digestion to noncombustible gases and a low volume noncombustible residue.

  12. First-principles modeling of materials for nuclear energy applications

    SciTech Connect (OSTI)

    Dmitriev, Andrey I. Nikonov, Anton Yu.; Ponomareva, Alena V.; Abrikosov, Igor A.; Barannikova, Svetlana A.

    2014-11-14

    We discuss recent developments in the field of ab initio electronic structure theory and its use for studies of materials for nuclear energy applications. We review state-of-the-art simulation methods that allow for an efficient treatment of effects due to chemical and magnetic disorder, and illustrate their predictive power with examples of two materials systems, Fe-Cr-Ni alloys and Zr-Nb alloys.

  13. Adhesion layer for etching of tracks in nuclear trackable materials

    DOE Patents [OSTI]

    Morse, Jeffrey D.; Contolini, Robert J.

    2001-01-01

    A method for forming nuclear tracks having a width on the order of 100-200 nm in nuclear trackable materials, such as polycarbonate (LEXAN) without causing delamination of the LEXAN. The method utilizes an adhesion film having a inert oxide which allows the track to be sufficiently widened to >200 nm without delamination of the nuclear trackable materials. The adhesion film may be composed of a metal such as Cr, Ni, Au, Pt, or Ti, or composed of a dielectric having a stable surface, such as silicon dioxide (SiO.sub.2), silicon nitride (SiN.sub.x), and aluminum oxide (AlO). The adhesion film can either be deposited on top of the gate metal layer, or if the properties of the adhesion film are adequate, it can be used as the gate layer. Deposition of the adhesion film is achieved by standard techniques, such as sputtering or evaporation.

  14. Facility Approvals, Security Surveys, and Nuclear Materials Surveys

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1992-09-15

    To establish Department of Energy (DOE) requirements for granting facility approvals prior to permitting safeguards and security interests on the premises and the conduct of insite security and/or nuclear material surveys of facilities with safeguards and security interests. Cancels DOE 5634.1A. Canceled by DOE O 470.1 dated 9-28-95.

  15. Facility Approvals, Security Surveys, and Nuclear Materials Surveys

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    1988-02-03

    To establish the Department of Energy (DOE) requirements for granting facility approvals prior to permitting safeguards and security interests on the premises and the conduct of on-site security and/or nuclear material surveys of facilities with safeguards and security interests. Cancels DOE O 5630.7 and DOE O 5634.1. Canceled by DOE 5634.1B.

  16. Storage of nuclear materials by encapsulation in fullerenes

    DOE Patents [OSTI]

    Coppa, Nicholas V. (Los Alamos, NM)

    1994-01-01

    A method of encapsulating radioactive materials inside fullerenes for stable long-term storage. Fullerenes provide a safe and efficient means of disposing of nuclear waste which is extremely stable with respect to the environment. After encapsulation, a radioactive ion is essentially chemically isolated from its external environment.

  17. Method for producing high surface area chromia materials for catalysis

    DOE Patents [OSTI]

    Gash, Alexander E. (Brentwood, CA); Satcher, Joe (Patterson, CA); Tillotson, Thomas (Tracy, CA); Hrubesh, Lawrence (Pleasanton, CA); Simpson, Randall (Livermore, CA)

    2007-05-01

    Nanostructured chromium(III)-oxide-based materials using sol-gel processing and a synthetic route for producing such materials are disclosed herein. Monolithic aerogels and xerogels having surface areas between 150 m.sup.2/g and 520 m.sup.2/g have been produced. The synthetic method employs the use of stable and inexpensive hydrated-chromium(III) inorganic salts and common solvents such as water, ethanol, methanol, 1-propanol, t-butanol, 2-ethoxy ethanol, and ethylene glycol, DMSO, and dimethyl formamide. The synthesis involves the dissolution of the metal salt in a solvent followed by an addition of a proton scavenger, such as an epoxide, which induces gel formation in a timely manner. Both critical point (supercritical extraction) and atmospheric (low temperature evaporation) drying may be employed to produce monolithic aerogels and xerogels, respectively.

  18. Technology Readiness Levels for Advanced Nuclear Fuels and Materials Development

    SciTech Connect (OSTI)

    Jon Carmack

    2014-01-01

    The Technology Readiness Level (TRL) process is used to quantitatively assess the maturity of a given technology. The TRL process has been developed and successfully used by the Department of Defense (DOD) for development and deployment of new technology and systems for defense applications. In addition, NASA has also successfully used the TRL process to develop and deploy new systems for space applications. Advanced nuclear fuels and materials development is a critical technology needed for closing the nuclear fuel cycle. Because the deployment of a new nuclear fuel forms requires a lengthy and expensive research, development, and demonstration program, applying the TRL concept to the advanced fuel development program is very useful as a management and tracking tool. This report provides definition of the technology readiness level assessment process as defined for use in assessing nuclear fuel technology development for the Advanced Fuel Campaign (AFC).

  19. Laboratory to demolish excavation enclosures at Material Disposal Area B

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    near DP road Excavation enclosures at MDA B Laboratory to demolish excavation enclosures at Material Disposal Area B near DP road Pre-demolition activities are beginning this week and the work should be completed by the end of March 2013. November 1, 2012 The Laboratory plans to demolish the enclosures used to safely excavate and clean up the Lab's oldest waste disposal site near DP Road in Los Alamos. The Laboratory plans to demolish the enclosures used to safely excavate and clean up the

  20. Laboratory to demolish excavation enclosures at Material Disposal Area B

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    near DP Road Excavation Enclosures At MDA B Laboratory to demolish excavation enclosures at Material Disposal Area B near DP Road Pre-demolition activities are beginning this week and the work should be completed by the end of March 2013. November 1, 2012 The Laboratory plans to demolish the enclosures used to safely excavate and clean up the Lab's oldest waste disposal site near DP Road in Los Alamos. The Laboratory plans to demolish the enclosures used to safely excavate and clean up the

  1. Laboratory to demolish excavation enclosures at Material Disposal Area B

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    near DP Road Excavation Enclosures At MDA B Laboratory to demolish excavation enclosures at Material Disposal Area B near DP Road Pre-demolition activities are beginning this week and the work should be completed by the end of March 2013. November 1, 2012 The Laboratory plans to demolish the enclosures used to safely excavate and clean up the Lab's oldest waste disposal site near DP Road in Los Alamos. The Laboratory plans to demolish the enclosures used to safely excavate and clean up the

  2. ADVANCED CERAMIC MATERIALS FOR NEXT-GENERATION NUCLEAR APPLICATIONS

    SciTech Connect (OSTI)

    Marra, J.

    2010-09-29

    Rising global energy demands coupled with increased environmental concerns point to one solution; they must reduce their dependence on fossil fuels that emit greenhouse gases. As the global community faces the challenge of maintaining sovereign nation security, reducing greenhouse gases, and addressing climate change nuclear power will play a significant and likely growing role. In the US, nuclear energy already provides approximately one-fifth of the electricity used to power factories, offices, homes, and schools with 104 operating nuclear power plants, located at 65 sites in 31 states. Additionally, 19 utilities have applied to the US Nuclear Regulatory Commission (NRC) for construction and operating licenses for 26 new reactors at 17 sites. This planned growth of nuclear power is occurring worldwide and has been termed the 'nuclear renaissance.' As major industrial nations craft their energy future, there are several important factors that must be considered about nuclear energy: (1) it has been proven over the last 40 years to be safe, reliable and affordable (good for Economic Security); (2) its technology and fuel can be domestically produced or obtained from allied nations (good for Energy Security); and (3) it is nearly free of greenhouse gas emissions (good for Environmental Security). Already an important part of worldwide energy security via electricity generation, nuclear energy can also potentially play an important role in industrial processes and supporting the nation's transportation sector. Coal-to-liquid processes, the generation of hydrogen and supporting the growing potential for a greatly increased electric transportation system (i.e. cars and trains) mean that nuclear energy could see dramatic growth in the near future as we seek to meet our growing demand for energy in cleaner, more secure ways. In order to address some of the prominent issues associated with nuclear power generation (i.e., high capital costs, waste management, and proliferation), the worldwide community is working to develop and deploy new nuclear energy systems and advanced fuel cycles. These new nuclear systems address the key challenges and include: (1) extracting the full energy value of the nuclear fuel; (2) creating waste solutions with improved long term safety; (3) minimizing the potential for the misuse of the technology and materials for weapons; (4) continually improving the safety of nuclear energy systems; and (5) keeping the cost of energy affordable.

  3. Design of standards for nondestructive assay of special nuclear material

    SciTech Connect (OSTI)

    Smith, H.A. Jr.; Stewart, J.E.; Ruhter W.

    1997-05-01

    Nondestructive assay (NDA) of special nuclear material (SNM) involves a variety of measurement techniques, instruments, and nuclear materials. High-quality measurements require well-characterized SNM standards that represent the expected range of mass, chemical composition, and physical properties of the SNM to be measured. Due to the very limited commercial availability of NDA standards, facilities must usually produce their own standards, both to meet their specific measurement needs and to comply with existing regulations. This paper will describe the current extent to which NDA standards are commercially available. The authors will further describe the types of NDA standards used to calibrate and verify the measurement techniques commonly used in the safeguards of SNM. Several types of NDA standards will be discussed in detail to illustrate the considerations that go into specifying and designing traceable, representative standards for materials accounting measurements.

  4. The Application of materials attractiveness in a graded approach to nuclear materials security

    SciTech Connect (OSTI)

    Ebbinghaus, B.; Bathke, C.; Dalton, D.; Murphy, J.

    2013-07-01

    The threat from terrorist groups has recently received greater attention. In this paper, material quantity and material attractiveness are addressed through the lens of a minimum security strategy needed to prevent the construction of a nuclear explosive device (NED) by an adversary. Nuclear materials are placed into specific security categories (3 or 4 categories) , which define a number of security requirements to protect the material. Materials attractiveness can be divided into four attractiveness levels, High, Medium, Low, and Very Low that correspond to the utility of the material to the adversary and to a minimum security strategy that is necessary to adequately protect the nuclear material. We propose a graded approach to materials attractiveness that recognizes for instance substantial differences in attractiveness between pure reactor-grade Pu oxide (High attractiveness) and fresh MOX fuel (Low attractiveness). In either case, an adversary's acquisition of a Category I quantity of plutonium would be a major incident, but the acquisition of Pu oxide by the adversary would be substantially worse than the acquisition of fresh MOX fuel because of the substantial differences in the time and complexity required of the adversary to process the material and fashion it into a NED.

  5. Materials and Sensor R&D to Transform the Nuclear Stockpile: Livermore?s

    Office of Scientific and Technical Information (OSTI)

    Transformational Materials Initiative (Technical Report) | SciTech Connect Materials and Sensor R&D to Transform the Nuclear Stockpile: Livermore?s Transformational Materials Initiative Citation Details In-Document Search Title: Materials and Sensor R&D to Transform the Nuclear Stockpile: Livermore?s Transformational Materials Initiative As the nation's nuclear weapons age and the demands placed on them change, significant challenges face the nuclear stockpile. Risks include material

  6. SAVANNAH RIVER SITE'S H-CANYON FACILITY: IMPACTS OF FOREIGN OBLIGATIONS ON SPECIAL NUCLEAR MATERIAL DISPOSITION

    SciTech Connect (OSTI)

    Magoulas, V.

    2013-06-03

    The US has a non-proliferation policy to receive foreign and domestic research reactor returns of spent fuel materials of US origin. These spent fuel materials are returned to the Department of Energy (DOE) and placed in storage in the L-area spent fuel basin at the Savannah River Site (SRS). The foreign research reactor returns fall subject to the 123 agreements for peaceful cooperation. These 123 agreements are named after section 123 of the Atomic Energy Act of 1954 and govern the conditions of nuclear cooperation with foreign partners. The SRS management of these foreign obligations while planning material disposition paths can be a challenge.

  7. Nuclear materials 1993 annual report. Volume 8, No. 2

    SciTech Connect (OSTI)

    1995-05-01

    This annual report of the US Nuclear Regulatory Commission`s Office for Analysis and Evaluation of Operational Data (AEOD) describes activities conducted during 1993. The report is published in two parts. NUREG-1272, Vol. 8, No. 1, covers power reactors and presents an overview of the operating experience of the nuclear power industry from the NRC perspective, including comments about the trends of some key performance measures. The report also includes the principal findings and issues identified in AEOD studies over the past year and summarizes information from such sources as licensee event reports, diagnostic evaluations, and reports to the NRC`s Operations Center. NUREG-1272, Vol. 8, No. 2, covers nuclear materials and presents a review of the events and concerns during 1993 associated with the use of licensed material in nonreactor applications, such as personnel overexposures and medical misadministrations. Note that the subtitle of No. 2 has been changed from ``Nonreactors`` to ``Nuclear Materials.`` Both reports also contain a discussion of the Incident Investigation Team program and summarize both the Incident Investigation Team and Augmented Inspection Team reports. Each volume contains a list of the AEOD reports issued from 1980 through 1993.

  8. X-ray backscatter imaging of nuclear materials

    DOE Patents [OSTI]

    Chapman, Jeffrey Allen; Gunning, John E; Hollenbach, Daniel F; Ott, Larry J; Shedlock, Daniel

    2014-09-30

    The energy of an X-ray beam and critical depth are selected to detect structural discontinuities in a material having an atomic number Z of 57 or greater. The critical depth is selected by adjusting the geometry of a collimator that blocks backscattered radiation so that backscattered X-ray originating from a depth less than the critical depth is not detected. Structures of Lanthanides and Actinides, including nuclear fuel rod materials, can be inspected for structural discontinuities such as gaps, cracks, and chipping employing the backscattered X-ray.

  9. UNCLASSIFIED UNCLASSIFIED Nuclear Materials Management & Safeguards System

    National Nuclear Security Administration (NNSA)

    UNCLASSIFIED Nuclear Materials Management & Safeguards System CONTACT INFORMATION UPDATE REPORTING IDENTIFICATION SYMBOL (RIS) RIS: Address: Facility Name: CONTACTS Name Email: Phone/Fax Name Email: Phone/Fax Name Email: Phone/Fax Name Email: Phone/Fax Return Via Mail To: U.S Department Of Energy ATTN: NMMSS Staff NA-73, GTN 1000 Independence Avenue, SW Washington, DC 20585-1290 Return Via Fax To: 301-903-1998 Return Via E-Mail To: NMMSS@nnsa.doe.gov

  10. Interactive Simulation of Nuclear Materials Safeguards and Security

    Energy Science and Technology Software Center (OSTI)

    1994-03-14

    THIEF is an interactive computer simulation or computer game of the safeguards and security (S&S) systems of a nuclear facility. The user is placed in the role of a non-violent insider attempting to remove special nuclear material from the facility. All portions of the S&S system that are relevant to the non-violent insider threat are included. The computer operates the S&S systems and attempts to detect the loss of the nuclear material. Both the physicalmore » protection system and the materials control and accounting system are modeled. The description of the facility and its S&S systems are defined by the user with the aid of an input module. All aspects of the facility description are provided by the user. The program has a custom graphical user interface to facilitate its use by people with limited computer experience. The custom interface also allows it to run on relatively small computer systems.« less

  11. Los Alamos National Laboratory standard nuclear material container

    SciTech Connect (OSTI)

    Stone, Timothy A

    2009-01-01

    The shut down of United States (U.S.) nuclear-weapons production activities in the early 1990s left large quantities of nuclear materials throughout the U.S. Department of Energy (DOE) complex in forms not intended for long-term storage. In May 1994, the Defense Nuclear Facilities Safety Board (DNFSB) issued Recommendation 94-1, which called for the stabilization and disposition of 'thousands of containers of plutonium-bearing liquids and solids' in the DOE complex, including LANL in the nuclear-weapons-manufacturing pipeline when manufacturing ended. This resulted in the development of the 3013 standard with container requirements for long term storage (up to 50 years). A follow on was the Criteria For Interim Storage of Plutonium Bearing Materials, Charles B. Curtis, in 1996 to address storage other than the 3013 standard for shorter time frames. In January 2000, the DNFSB issued Recommendation 2000-1, which stated the need for LANL to repackage 'about one ton of plutonium metal and oxide,' declared excess to Defense Program (DP) needs. The DNFSB recommended that LANL 'stabilize and seal within welded containers with an inert atmosphere the plutonium oxides ... which are not yet in states conforming to the long-term storage envisaged by DOE-STD-3013,' and that they '... enclose existing and newly-generated legacy plutonium metal in sealed containers with an inert atmosphere,' and 'remediate and/or safely store the various residues.' Recommendation 2000-1, while adding to the number of items needing remediation, also reiterated the need to address remaining items from 1994-1 in a timely fashion. Since timetables slipped, the DNFSB recommended that the Complex 'prioritize and schedule tasks according to the consideration of risks.' In March 2005, the DNFSB issued Recommendation 2005-1. This recommendation addresses the need for a consistent set of criteria across the DOE complex for the interim storage of nuclear material packaged outside an engineered barrier. The Department of Energy (DOE) approved and issued on March 7, 2008, DOE M 441.1-1, Nuclear Material Packaging Manual [hereafter referred to as Manual] to address this recommendation, and a Prioritization Methodology as a complex-wide requirement for the packaging of nuclear material outside an engineered barrier. The Manual establishes 'technically justified criteria' for packages in order to ensure safe interim storage and handling outside an engineered barrier. The Prioritization Methodology establishes a risk-based procedure for identifying the order to repackage that would most efficiently reduce the overall risk. It is a logical extension of the work performed to meet the two earlier DNFSB recommendations to include all materials stored outside of engineered barriers, i.e., not just excess materials. LANL will continue to work all aspects of a comprehensive Implementation Plan to d monstrate all aspects of compliance with the Manual. Assessment of materials in nonstandard containers utilizing a risk based approach, repackaging up to 400 containers/year; activities include reprocessing of items to allow container consolidation and subsequent increase in vault capacity. Continued efforts in establishing and implementing a Surveillance and Maintenance Program for current Hagans and for the NG SNMCSs supported by a database for packaging and surveillance. Elastomer aging studies for the NG SNMCs will continue to justify extending the design life well beyond the currently specified five years. First production with containers available for use anticipated in June 2010. LANL will continue to define schedule and resources to meet these objectives.

  12. Materials and Sensor R&D to Transform the Nuclear Stockpile:...

    Office of Scientific and Technical Information (OSTI)

    Title: Materials and Sensor R&D to Transform the Nuclear Stockpile: Livermore?s Transformational Materials Initiative As the nation's nuclear weapons age and the demands placed on ...

  13. W.T.; Rainey, R.H. 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS;...

    Office of Scientific and Technical Information (OSTI)

    thorium fuel reprocessing experience Brooksbank, R.E.; McDuffee, W.T.; Rainey, R.H. 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; NUCLEAR MATERIALS DIVERSION; SAFEGUARDS; SPENT FUELS;...

  14. Radiological Modeling for Determination of Derived Concentration Levels of an Area with Uranium Residual Material - 13533

    SciTech Connect (OSTI)

    Perez-Sanchez, Danyl [CIEMAT, Avenida Complutense 40, 28040, Madrid (Spain)] [CIEMAT, Avenida Complutense 40, 28040, Madrid (Spain)

    2013-07-01

    As a result of a pilot project developed at the old Spanish 'Junta de Energia Nuclear' to extract uranium from ores, tailings materials were generated. Most of these residual materials were sent back to different uranium mines, but a small amount of it was mixed with conventional building materials and deposited near the old plant until the surrounding ground was flattened. The affected land is included in an area under institutional control and used as recreational area. At the time of processing, uranium isotopes were separated but other radionuclides of the uranium decay series as Th-230, Ra-226 and daughters remain in the residue. Recently, the analyses of samples taken at different ground's depths confirmed their presence. This paper presents the methodology used to calculate the derived concentration level to ensure that the reference dose level of 0.1 mSv y-1 used as radiological criteria. In this study, a radiological impact assessment was performed modeling the area as recreational scenario. The modelization study was carried out with the code RESRAD considering as exposure pathways, external irradiation, inadvertent ingestion of soil, inhalation of resuspended particles, and inhalation of radon (Rn-222). As result was concluded that, if the concentration of Ra-226 in the first 15 cm of soil is lower than, 0.34 Bq g{sup -1}, the dose would not exceed the reference dose. Applying this value as a derived concentration level and comparing with the results of measurements on the ground, some areas with a concentration of activity slightly higher than latter were found. In these zones the remediation proposal has been to cover with a layer of 15 cm of clean material. This action represents a reduction of 85% of the dose and ensures compliance with the reference dose. (authors)

  15. Nuclear Material Control and Accountability (NMC&A) for the Savannah...

    Office of Environmental Management (EM)

    Material Control and Accountability (NMC&A) for the Savannah River Site Tritium Facilities Nuclear Material Control and Accountability (NMC&A) for the Savannah River Site Tritium...

  16. Vapor etching of nuclear tracks in dielectric materials

    DOE Patents [OSTI]

    Musket, Ronald G. (Danville, CA); Porter, John D. (Berkeley, CA); Yoshiyama, James M. (Fremont, CA); Contolini, Robert J. (Lake Oswego, OR)

    2000-01-01

    A process involving vapor etching of nuclear tracks in dielectric materials for creating high aspect ratio (i.e., length much greater than diameter), isolated cylindrical holes in dielectric materials that have been exposed to high-energy atomic particles. The process includes cleaning the surface of the tracked material and exposing the cleaned surface to a vapor of a suitable etchant. Independent control of the temperatures of the vapor and the tracked materials provide the means to vary separately the etch rates for the latent track region and the non-tracked material. As a rule, the tracked regions etch at a greater rate than the non-tracked regions. In addition, the vapor-etched holes can be enlarged and smoothed by subsequent dipping in a liquid etchant. The 20-1000 nm diameter holes resulting from the vapor etching process can be useful as molds for electroplating nanometer-sized filaments, etching gate cavities for deposition of nano-cones, developing high-aspect ratio holes in trackable resists, and as filters for a variety of molecular-sized particles in virtually any liquid or gas by selecting the dielectric material that is compatible with the liquid or gas of interest.

  17. State Systems of Accounting for and Control of Nuclear Material | National

    National Nuclear Security Administration (NNSA)

    Nuclear Security Administration State Systems of Accounting for and Control of Nuclear Material | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets

  18. Safeguards Measurement Evaluation Program nuclear materials measurement data: Phase 1: Final report, 1985 through 1986

    SciTech Connect (OSTI)

    Cacic, C.G.

    1988-08-01

    The New Brunswick Laboratory has been tasked by the US Department of Energy Office of Safeguards and Security to assess and evaluate the adequacy of measurement technology as applied to materials accounting in US Department of Energy nuclear facilities. The Safeguards Measurement Evaluation Program was developed as a means to monitor and evaluate the quality and effectiveness of accounting measurements by site, material balance area, or unit process. Phase 1 of the Safeguards Measurement Evaluation Program, initiated during 1985, involved evaluation of the primary accountability measurement methods at six US Department of Energy Defense Programs facilities. Resulting data are presented and evaluated as indicators of current state-of-the-practice accountability measurement methodology, deficiencies in materials accounting practices, and areas for possible assistance in upgrading measurement capabilities. 22 figs., 5 tabs.

  19. Neutron interrogation system using high gamma ray signature to detect contraband special nuclear materials in cargo

    DOE Patents [OSTI]

    Slaughter, Dennis R.; Pohl, Bertram A.; Dougan, Arden D.; Bernstein, Adam; Prussin, Stanley G.; Norman, Eric B.

    2008-04-15

    A system for inspecting cargo for the presence of special nuclear material. The cargo is irradiated with neutrons. The neutrons produce fission products in the special nuclear material which generate gamma rays. The gamma rays are detecting indicating the presence of the special nuclear material.

  20. Special nuclear materials cutoff exercise: Issues and lessons learned. Volume 3

    SciTech Connect (OSTI)

    Libby, R.A.; Segal, J.E.; Stanbro, W.D.; Davis, C.

    1995-08-01

    This document is appendices D-J for the Special Nuclear Materials Cutoff Exercise: Issues and Lessons Learned. Included are discussions of the US IAEA Treaty, safeguard regulations for nuclear materials, issue sheets for the PUREX process, and the LANL follow up activity for reprocessing nuclear materials.

  1. Proceedings of the symposium on Nuclear Radiation Detection Materials

    SciTech Connect (OSTI)

    Perry, D.L.; Burger, A.; Franks, L.; Schieber, M.

    2008-07-01

    This symposium provides a venue for the presentation of the latest results and discussion of radiation detection materials from both experimental and theoretical standpoints. As advances are made in this area of materials, additional experimental and theoretical approaches are used to both guide the growth of materials and to characterize the materials that have a wide array of applications for detecting different types of radiation. The types of detector materials for semiconductors and scintillators include a variety of molecular compounds such as lanthanum halides (LaX{sub 3}), zinc oxide (ZnO), lead iodide (PbI{sub 2}), cadmium telluride (CdTe), mercuric iodide (HgI{sub 2}), thallium bromide (TlBr), as well as others, such as cadmium zinc telluride (CZT). An additional class of scintillators includes those based on organic compounds and glasses. Ideally, desired materials used for radiation detection have attributes such as appropriate-range band-gaps, high atomic numbers of the central element, high densities, performance at room temperature, and strong mechanical properties, and are low cost in terms of their production. There are significant gaps in the knowledge related to these materials that are very important in making radiation detector materials that are higher quality in terms of their reproducible purity, homogeneity, and mechanical integrity. The topics that are the focal point of this symposium address these issues so that much better detectors may be made in the future. Topics cover the following areas: - Material growth: on-going developments regarding cadmium telluride (CdTe), cadmium zinc telluride (CZT), mercuric iodide (HgI{sub 2}), cadmium manganese telluride (CMT), LaX{sub 3}, and all other detector materials; new materials with potential for radiation detection (II-VI, III-VI, III-VII compounds, neutron detectors, nano-materials, and ceramic scintillators); purification techniques; and growth methods; - Characterization: experimental results; methodologies; defect structure; surface and bulk effects; and interfacial phenomena (contacting, contact adhesion, crystallographic polarity, Schottky barrier, and surface passivation); - Physical and mechanical properties: electric charge compensation mechanisms, charge collection, and thermal transport; hardness; and plasticity; - New and innovative characterization techniques: optical spectroscopy; microscopy (SEM, TEM, STM, AFM, etc.); synchrotron mapping and X-ray diffraction; rocking curves; and spectroscopy (IR, Raman, NMR, XPS, Auger, and other applicable approaches); - Theoretical studies: bandgap calculations; mobility calculations; scintillator material physics; thermal modeling; crystal growth; processes in material matrices; and processes in amorphous and crystalline matrices.

  2. U.S. and Russian Collaboration in the Area of Nuclear Forensics

    SciTech Connect (OSTI)

    Kristo, M J

    2007-10-22

    Nuclear forensics has become increasingly important in the fight against illicit trafficking in nuclear and other radioactive materials. The illicit trafficking of nuclear materials is, of course, an international problem; nuclear materials may be mined and milled in one country, manufactured in a second country, diverted at a third location, and detected at a fourth. There have been a number of articles in public policy journals in the past year that call for greater interaction between the U. S. and the rest of the world on the topic of nuclear forensics. Some believe that such international cooperation would help provide a more certain capability to identify the source of the nuclear material used in a terrorist event. An improved international nuclear forensics capability would also be important as part of the IAEA verification toolkit, particularly linked to increased access provided by the additional protocol. A recent study has found that, although international progress has been made in securing weapons-usable HEU and Pu, the effort is still insufficient. They found that nuclear material, located in 40 countries, could be obtained by terrorists and criminals and used for a crude nuclear weapon. Through 2006, the IAEA Illicit Trafficking Database had recorded a total of 607 confirmed events involving illegal possession, theft, or loss of nuclear and other radioactive materials. Although it is difficult to predict the future course of such illicit trafficking, increasingly such activities are viewed as significant threats that merit the development of special capabilities. As early as April, 1996, nuclear forensics was recognized at the G-8 Summit in Moscow as an important element of an illicit nuclear trafficking program. Given international events over the past several years, the value and need for nuclear forensics seems greater than ever. Determining how and where legitimate control of nuclear material was lost and tracing the route of the material from diversion through interdiction are important goals for nuclear forensics and attribution. It is equally important to determine whether additional devices or materials that pose a threat to public safety are also available. Finding the answer to these questions depends on determining the source of the material and its method of production. Nuclear forensics analysis and interpretation provide essential insights into methods of production and sources of illicit radioactive materials. However, they are most powerful when combined with other sources of information, including intelligence and traditional detective work. The certainty of detection and punishment for those who remove nuclear materials from legitimate control provides the ultimate deterrent for such diversion and, ultimately, for the intended goal of such diversion, including nuclear terrorism or proliferation. Consequently, nuclear forensics is an integral part of 'nuclear deterrence' in the 21st century. Nuclear forensics will always be limited by the diagnostic information inherent in the interdicted material. Important markers for traditional forensics (fingerprints, stray material, etc.) can be eliminated or obscured, but many nuclear materials have inherent isotopic or chemical characteristics that serve as unequivocal markers of specific sources, production processes, or transit routes. The information needed for nuclear forensics goes beyond that collected for most commercial and international verification activities. Fortunately, the international nuclear engineering enterprise has a restricted number of conspicuous process steps that makes the interpretation process easier. Ultimately, though, it will always be difficult to distinguish between materials that reflect similar source or production histories, but are derived from disparate sites. Due to the significant capital costs of the equipment and the specialized expertise of the personnel, work in the field of nuclear forensics has been restricted so far to a handful of national and international laboratories. There are a limited number of

  3. DOE nuclear material packaging manual: storage container requirements for plutonium oxide materials

    SciTech Connect (OSTI)

    Veirs, D Kirk

    2009-01-01

    Loss of containment of nuclear material stored in containers such as food-pack cans, paint cans, or taped slip lid cans has generated concern about packaging requirements for interim storage of nuclear materials in working facilities such as the plutonium facility at Los Alamos National Laboratory (LANL). In response, DOE has recently issued DOE M 441.1 'Nuclear Material Packaging Manual' with encouragement from the Defense Nuclear Facilities Safety Board. A unique feature compared to transportation containers is the allowance of filters to vent flammable gases during storage. Defining commonly used concepts such as maximum allowable working pressure and He leak rate criteria become problematic when considering vented containers. Los Alamos has developed a set of container requirements that are in compliance with 441.1 based upon the activity of heat-source plutonium (90% Pu-238) oxide, which bounds the requirements for weapons-grade plutonium oxide. The pre and post drop-test He leak rates depend upon container size as well as the material contents. For containers that are routinely handled, ease of handling and weight are a major consideration. Relatively thin-walled containers with flat bottoms are desired yet they cannot be He leak tested at a differential pressure of one atmosphere due to the potential for plastic deformation of the flat bottom during testing. The He leak rates and He leak testing configuration for containers designed for plutonium bearing materials will be presented. The approach to meeting the other manual requirements such as corrosion and thermal degradation resistance will be addressed. The information presented can be used by other sites to evaluate if their conditions are bounded by LANL requirements when considering procurement of 441.1 compliant containers.

  4. Conceptual design report: Nuclear materials storage facility renovation. Part 1, Design concept. Part 2, Project management

    SciTech Connect (OSTI)

    1995-07-14

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This document provides Part I - Design Concept which describes the selected solution, and Part II - Project Management which describes the management system organization, the elements that make up the system, and the control and reporting system.

  5. Conceptual design report: Nuclear materials storage facility renovation. Part 7, Estimate data

    SciTech Connect (OSTI)

    1995-07-14

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. This report is organized according to the sections and subsections outlined by Attachment III-2 of DOE Document AL 4700.1, Project Management System. It is organized into seven parts. This document, Part VII - Estimate Data, contains the project cost estimate information.

  6. Conceptual design report: Nuclear materials storage facility renovation. Part 3, Supplemental information

    SciTech Connect (OSTI)

    1995-07-14

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. It is organized into seven parts. Part I - Design Concept describes the selected solution. Part III - Supplemental Information contains calculations for the various disciplines as well as other supporting information and analyses.

  7. Measurement and Characterization of Nuclear Material at Idaho National Laboratory

    SciTech Connect (OSTI)

    J. L. Dolan; M. Flaska; S. A. Pozzi; D. L. Chichester

    2009-07-01

    A measurement plan and preliminary Monte Carlo simulations are presented for the investigation of well-defined mixed-oxide fuel pins. Measurement analysis including pulse-height distributions and time-dependent cross-correlation functions will be performed separately for neutrons and gamma rays. The utilization of Monte Carlo particle transport codes, specifically MCNP-PoliMi, is discussed in conjunction with the anticipated measurements. Four EJ-309 liquid scintillation detectors with an accurate pulse timing and digital, offline, optimized pulse-shape discrimination method will be used to prove the dependency of pulse-height distributions, cross-correlation functions, and material multiplicities upon fuel pin composition, fuel pin quantity, and detector geometry. The objective of the measurements and simulations is to identify novel methods for describing mixed-oxide fuel samples by relating measured quantities to fuel characteristics such as criticality, mass quantity, and material composition. This research has applications in nuclear safeguards and nonproliferation.

  8. Nuclear Materials Management U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO)

    SciTech Connect (OSTI)

    Jesse Schrieber

    2008-07-01

    In light of the changing Defense Complex mission, the high cost to storing and protecting nuclear materials, and in consideration of scarcity of resources, it is imperative that the U.S. Department of Energy (DOE) owned nuclear materials are managed effectively. The U.S. Department of Energy, National Nuclear Security Administration (NNSA) Strategic Action Plan outlines the strategy for continuing to meet Americas nuclear security goals, meeting the overall mission challenges of DOE and NNSA as well as giving focus to local missions. The mission of the NNSA/NSO Nuclear Materials Management (NMM) Program is to ensure that nuclear material inventories are accurately assessed and reported, future material needs are adequately planned, and that existing Nevada Test Site (NTS) inventories are efficiently utilized, staged, or dispositioned. The NNSA/NSO understands that the NTS has unique characteristics to serve and benefit the nation with innovative solutions to the complex problems involving Special Nuclear Materials, hazardous materials, and multi-agency, integrated operations. The NNSA/NSO is defining infrastructure requirements for known future missions, developing footprint consolidation strategic action plans, and continuing in the path of facility modernization and improvements. The NNSA/NSO is striving for the NTS to be acknowledged as an ideal location towards mission expansion and growth. The NTS has the capability of providing isolated, large scale construction and development locations for nuclear power or alternate energy source facilities, expanded nuclear material storage sites, and for new development in green technology.

  9. Nuclear Materials Management U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO)

    SciTech Connect (OSTI)

    Jesse Schreiber

    2008-03-01

    In light of the changing Defense Complex mission, the high cost to storing and protecting nuclear materials, and in consideration of scarcity of resources, it is imperative that the U.S. Department of Energy (DOE) owned nuclear materials are managed effectively. The U.S. Department of Energy, National Nuclear Security Administration (NNSA) Strategic Action Plan outlines the strategy for continuing to meet Americas nuclear security goals, meeting the overall mission challenges of DOE and NNSA as well as giving focus to local missions. The mission of the NNSA/NSO Nuclear Materials Management (NMM) Program is to ensure that nuclear material inventories are accurately assessed and reported, future material needs are adequately planned, and that existing Nevada Test Site (NTS) inventories are efficiently utilized, staged, or dispositioned. The NNSA/NSO understands that the NTS has unique characteristics to serve and benefit the nation with innovative solutions to the complex problems involving Special Nuclear Materials, hazardous materials, and multi-agency, integrated operations. The NNSA/NSO is defining infrastructure requirements for known future missions, developing footprint consolidation strategic action plans, and continuing in the path of facility modernization improvements. The NNSA/NSO is striving for the NTS to be acknowledged as an ideal location towards mission expansion and growth. The NTS has the capability of providing isolated, large scale construction and development locations for nuclear power or alternate energy source facilities, expanded nuclear material storage sites, and for new development in green technology.

  10. NUCLEAR MATERIAL ATTRACTIVENESS: AN ASSESSMENT OF MATERIAL FROM PHWR'S IN A CLOSED THORIUM FUEL CYCLE

    SciTech Connect (OSTI)

    Sleaford, B W; Collins, B A; Ebbinghaus, B B; Bathke, C G; Prichard, A W; Wallace, R K; Smith, B W; Hase, K R; Bradley, K S; Robel, M; Jarvinen, G D; Ireland, J R; Johnson, M W

    2010-04-26

    This paper examines the attractiveness of material mixtures containing special nuclear materials (SNM) associated with reprocessing and the thorium-based LWR fuel cycle. This paper expands upon the results from earlier studies that examined the attractiveness of SNM associated with the reprocessing of spent light water reactor (LWR) fuel by various reprocessing schemes and the recycle of plutonium as a mixed oxide (MOX) fuel in LWR. This study shows that {sup 233}U that is produced in thorium-based fuel cycles is very attractive for weapons use. Consistent with other studies, these results also show that all fuel cycles examined to date need to be rigorously safeguarded and provided moderate to high levels of physical protection. These studies were performed at the request of the United States Department of Energy (DOE), and are based on the calculation of 'attractiveness levels' that has been couched in terms chosen for consistency with those normally used for nuclear materials in DOE nuclear facilities. The methodology and key findings will be presented.

  11. Rapid response sensor for analyzing Special Nuclear Material

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Mitra, S. S.; Doron, O.; Chen, A. X.; Antolak, A. J.

    2015-06-18

    Rapid in-situ analytical techniques are attractive for characterizing Special Nuclear Material (SNM). Present techniques are time consuming, and require sample dissolution. Proof-of-principal studies are performed to demonstrate the utility of employing low energy neutrons from a portable pulsed neutron generator for non-destructive isotopic analysis of nuclear material. In particular, time-sequenced data acquisition, operating synchronously with the pulsing of a neutron generator, partitions the characteristic elemental prompt gamma-rays according to the type of the reaction; inelastic neutron scattering reactions during the ON state and thermal neutron capture reactions during the OFF state of the generator. Thus, the key challenge is isolatingmore » these signature gamma- rays from the prompt fission and β-delayed gamma-rays that are also produced during the neutron interrogation. A commercial digital multi-channel analyzer has been specially customized to enable time-resolved gamma-ray spectral data to be acquired in multiple user-defined time bins within each of the ON/OFF gate periods of the neutron generator. Preliminary results on new signatures from depleted uranium as well as modeling and benchmarking of the concept are presented, however this approach should should be applicable for virtually all forms of SNM.« less

  12. Rapid response sensor for analyzing Special Nuclear Material

    SciTech Connect (OSTI)

    Mitra, S. S.; Doron, O.; Chen, A. X.; Antolak, A. J.

    2015-06-18

    Rapid in-situ analytical techniques are attractive for characterizing Special Nuclear Material (SNM). Present techniques are time consuming, and require sample dissolution. Proof-of-principal studies are performed to demonstrate the utility of employing low energy neutrons from a portable pulsed neutron generator for non-destructive isotopic analysis of nuclear material. In particular, time-sequenced data acquisition, operating synchronously with the pulsing of a neutron generator, partitions the characteristic elemental prompt gamma-rays according to the type of the reaction; inelastic neutron scattering reactions during the ON state and thermal neutron capture reactions during the OFF state of the generator. Thus, the key challenge is isolating these signature gamma- rays from the prompt fission and ?-delayed gamma-rays that are also produced during the neutron interrogation. A commercial digital multi-channel analyzer has been specially customized to enable time-resolved gamma-ray spectral data to be acquired in multiple user-defined time bins within each of the ON/OFF gate periods of the neutron generator. Preliminary results on new signatures from depleted uranium as well as modeling and benchmarking of the concept are presented, however this approach should should be applicable for virtually all forms of SNM.

  13. U.S. Works With Kazakhstan to Stop Nuclear and Radioactive Material

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Smuggling | Department of Energy Works With Kazakhstan to Stop Nuclear and Radioactive Material Smuggling U.S. Works With Kazakhstan to Stop Nuclear and Radioactive Material Smuggling May 6, 2006 - 10:34am Addthis WASHINGTON, DC - As part of the overall U.S. strategy to prevent nuclear and dangerous radiological materials from falling into the hands of terrorists, the Department of Energy's National Nuclear Security Administration (NNSA) announced today that an agreement with the government

  14. Neutron Detectors for Detection of Nuclear Materials at LANL| U.S. DOE

    Office of Science (SC) Website

    Office of Science (SC) Neutron Detectors for Detection of Nuclear Materials at LANL Nuclear Physics (NP) NP Home About Research Facilities Science Highlights Benefits of NP Applications of Nuclear Science Applications of Nuclear Science Archives Small Business Innovation / Technology Transfer Funding Opportunities Nuclear Science Advisory Committee (NSAC) Community Resources Contact Information Nuclear Physics U.S. Department of Energy SC-26/Germantown Building 1000 Independence Ave., SW

  15. Microsoft PowerPoint - Programmatic Update Nuclear Material Landscape_Richard Meehan [Compatibility Mode]

    National Nuclear Security Administration (NNSA)

    Programmatic Update - Nuclear Materials Landscape Richard Meehan, Director Office of Nuclear Material Integration (ONMI) NNSA Purpose  Provide an update on range of programmatic activities focused on: - Nuclear materials management and integration - Decision-making needs and stakeholders - Recent NMMSS developments  Highlight learning opportunities at NMMSS 2015 2 ONMI Programmatic Focus  Material management policy, plans, and expectations  Analysis and integration of DOE/NNSA-wide

  16. Hybrid statistical testing for nuclear material accounting data and/or process monitoring data in nuclear safeguards

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Burr, Tom; Hamada, Michael S.; Ticknor, Larry; Sprinkle, James

    2015-01-01

    The aim of nuclear safeguards is to ensure that special nuclear material is used for peaceful purposes. Historically, nuclear material accounting (NMA) has provided the quantitative basis for monitoring for nuclear material loss or diversion, and process monitoring (PM) data is collected by the operator to monitor the process. PM data typically support NMA in various ways, often by providing a basis to estimate some of the in-process nuclear material inventory. We develop options for combining PM residuals and NMA residuals (residual = measurement - prediction), using a hybrid of period-driven and data-driven hypothesis testing. The modified statistical tests canmore » be used on time series of NMA residuals (the NMA residual is the familiar material balance), or on a combination of PM and NMA residuals. The PM residuals can be generated on a fixed time schedule or as events occur.« less

  17. Hybrid statistical testing for nuclear material accounting data and/or process monitoring data in nuclear safeguards

    SciTech Connect (OSTI)

    Burr, Tom; Hamada, Michael S.; Ticknor, Larry; Sprinkle, James

    2015-01-01

    The aim of nuclear safeguards is to ensure that special nuclear material is used for peaceful purposes. Historically, nuclear material accounting (NMA) has provided the quantitative basis for monitoring for nuclear material loss or diversion, and process monitoring (PM) data is collected by the operator to monitor the process. PM data typically support NMA in various ways, often by providing a basis to estimate some of the in-process nuclear material inventory. We develop options for combining PM residuals and NMA residuals (residual = measurement - prediction), using a hybrid of period-driven and data-driven hypothesis testing. The modified statistical tests can be used on time series of NMA residuals (the NMA residual is the familiar material balance), or on a combination of PM and NMA residuals. The PM residuals can be generated on a fixed time schedule or as events occur.

  18. Termination of Safeguards for Accountable Nuclear Materials at the Idaho National Laboratory

    SciTech Connect (OSTI)

    Michael Holzemer; Alan Carvo

    2012-04-01

    Termination of safeguards ends requirements of Nuclear Material Control and Accountability (MC&A) and thereby removes the safeguards basis for applying physical protection requirements for theft and diversion of nuclear material, providing termination requirements are met as described. Department of Energy (DOE) M 470.4 6 (Nuclear Material Control and Accountability [8/26/05]) stipulates: 1. Section A, Chapter I (1)( q) (1): Safeguards can be terminated on nuclear materials provided the following conditions are met: (a) 'If the material is special nuclear material (SNM) or protected as SNM, it must be attractiveness level E and have a measured value.' (b) 'The material has been determined by DOE line management to be of no programmatic value to DOE.' (c) 'The material is transferred to the control of a waste management organization where the material is accounted for and protected in accordance with waste management regulations. The material must not be collocated with other accountable nuclear materials.' Requirements for safeguards termination depend on the safeguards attractiveness levels of the material. For attractiveness level E, approval has been granted from the DOE Idaho Operations Office (DOE ID) to Battelle Energy Alliance, LLC (BEA) Safeguards and Security (S&S). In some cases, it may be necessary to dispose of nuclear materials of attractiveness level D or higher. Termination of safeguards for such materials must be approved by the Departmental Element (this is the DOE Headquarters Office of Nuclear Energy) after consultation with the Office of Security.

  19. Nuclear Materials Safeguards and Security Upgrade Project | National...

    National Nuclear Security Administration (NNSA)

    Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response ...

  20. Nuclear Materials Technology Division/Los Alamos National Laboratory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    One of the new and daunting challenges in nuclear waste management is the disposition of plutonium recovered from dismantled nuclear weapons. Under the first and second Strategic ...

  1. Nuclear Materials Technology/Los Alamos National Laboratory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    6 Can Los Alamos Meet Its Future Nuclear Challenges? 9 Detecting and Predicting ... These powerful little "nuclear batteries" produce heat from the decay of radioac- tive ...

  2. Radiation effects in nuclear materials: Role of nuclear and electronic energy losses and their synergy

    SciTech Connect (OSTI)

    Thom, Lionel; Debelle, Aurelien; Garrido, Frederico; Mylonas, Stamatis; Dcamps, B.; Bachelet, C.; Sattonnay, G.; Pellegrino, S.; Miro, S.; Trocellier, P.; Serruys, Y.; Velisa, G.; Grygiel, C.; Monnet, I.; Toulemonde, Marcel; Simon, P.; Jagielski, Jacek; Jozwik-Biala, Iwona; Nowicki, Lech; Behar, M.; Weber, William J; Zhang, Yanwen; Backman, Marie; Nordlund, Kai; Djurabekova, Flyura

    2013-01-01

    Ceramic oxides and carbides are promising matrices for the immobilization and/or transmutation of nuclear wastes, cladding materials for gas-cooled fission reactors and structural components for fusion reactors. For these applications there is a need of fundamental data concerning the behavior of nuclear ceramics upon irradiation. This article is focused on the presentation of a few remarkable examples regarding ion-beam modifications of nuclear ceramics with an emphasis on the mechanisms leading to damage creation and phase transformations. Results obtained by combining advanced techniques (Rutherford backscattering spectrometry and channeling, X-ray diffraction, transmission electron microscopy, Raman spectroscopy) concern irradiations in a broad energy range (from keV to GeV) with the aim of exploring both nuclear collision (Sn) and electronic excitation (Se) regimes. Finally, the daunting challenge of the demonstration of the existence of synergistic effects between Sn and Se is tackled by discussing the healing due to intense electronic energy deposition (SHIBIEC) and by reporting results recently obtained in dual-beam irradiation (DBI) experiments.

  3. Selection of Corrosion Resistant Materials for Nuclear Waste Repositories

    SciTech Connect (OSTI)

    R.B. Rebak

    2006-08-28

    Several countries are considering geological repositories to dispose of nuclear waste. The environment of most of the currently considered repositories will be reducing in nature, except for the repository in the US, which is going to be oxidizing. For the reducing repositories, alloys such as carbon steel, stainless steels and titanium are being evaluated. For the repository in the US, some of the most corrosion resistant commercially available alloys are being investigated. This paper presents a summary of the behavior of the different materials under consideration for the repositories and the current understanding of the degradation modes of the proposed alloys in ground water environments from the point of view of general corrosion, localized corrosion and environmentally assisted cracking.

  4. SOFTWARE TOOLS THAT ADDRESS HAZARDOUS MATERIAL ISSUES DURING NUCLEAR FACILITY D and D

    SciTech Connect (OSTI)

    M. COURNOYER; R. GRUNDEMANN

    2001-03-01

    The 49-year-old Chemistry and Metallurgy Research (CMR) Facility is where analytical chemistry and metallurgical studies on samples of plutonium and nuclear materials are conduct in support of the Department of Energy's nuclear weapons program. The CMR Facility is expected to be decontaminated and decommissioned (D and D) over the next ten to twenty years. Over the decades, several hazardous material issues have developed that need to be address. Unstable chemicals must be properly reassigned or disposed of from the workspace during D and D operation. Materials that have critical effects that are primarily chronic in nature, carcinogens, reproductive toxin, and materials that exhibit high chronic toxicity, have unique decontamination requirements, including the decontrolling of areas where these chemicals were used. Certain types of equipment and materials that contain mercury, asbestos, lead, and polychlorinated biphenyls have special provisions that must be addressed. Utilization of commercially available software programs for addressing hazardous material issues during D and D operations such as legacy chemicals and documentation are presented. These user-friendly programs eliminate part of the tediousness associated with the complex requirements of legacy hazardous materials. A key element of this approach is having a program that inventories and tracks all hazardous materials. Without an inventory of chemicals stored in a particular location, many important questions pertinent to D and D operations can be difficult to answer. On the other hand, a well-managed inventory system can address unstable and highly toxic chemicals and hazardous material records concerns before they become an issue. Tapping into the institutional database provides a way to take advantage of the combined expertise of the institution in managing a cost effective D and D program as well as adding a quality assurance element to the program. Using laboratory requirements as a logic flow diagram, quality and cost effective methods are used to provide necessary information of programmatic, quality, and safety issues concerns. In summary, by seamlessly managing non-programmatic issues, chemical software programs allow scientists in nuclear research facilities more time to concentrate on their technical areas of interest.

  5. Nuclear Materials Safeguards and Security Upgrade Project Completed Under

    National Nuclear Security Administration (NNSA)

    Budget | National Nuclear Security Administration Completed Under Budget | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases

  6. Commission. The Nuclear Materials Management and Safeguards System (NMMSS) 2014 Annual Users

    National Nuclear Security Administration (NNSA)

    April 2014 NMMSS News is sponsored by the Department of Energy and the Nuclear Regulatory Commission. The Nuclear Materials Management and Safeguards System (NMMSS) 2014 Annual Users Training Meeting will be held May 12-15, 2014, in Denver, Colorado. NMMSS is the U.S. Government's official information system containing current and historical accounting data and other related nuclear material information collected from both government and commercial nuclear facilities. The data serve a critical

  7. Manual for Nuclear Materials Management and Safeguards System Reporting and Data Submission

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2003-08-19

    The manual provides detailed instructions for documenting and reporting data submissions for nuclear materials transactions, inventories, and material balances to the Nuclear Materials Management and Safeguards System (NMMSS). Cancels DOE M 474.1-2. Canceled by DOE M 470.4-6.

  8. Vital area identification for U.S. Nuclear Regulatory Commission nuclear power reactor licensees and new reactor applicants.

    SciTech Connect (OSTI)

    Whitehead, Donnie Wayne; Varnado, G. Bruce

    2008-09-01

    U.S. Nuclear Regulatory Commission nuclear power plant licensees and new reactor applicants are required to provide protection of their plants against radiological sabotage, including the placement of vital equipment in vital areas. This document describes a systematic process for the identification of the minimum set of areas that must be designated as vital areas in order to ensure that all radiological sabotage scenarios are prevented. Vital area identification involves the use of logic models to systematically identify all of the malicious acts or combinations of malicious acts that could lead to radiological sabotage. The models available in the plant probabilistic risk assessment and other safety analyses provide a great deal of the information and basic model structure needed for the sabotage logic model. Once the sabotage logic model is developed, the events (or malicious acts) in the model are replaced with the areas in which the events can be accomplished. This sabotage area logic model is then analyzed to identify the target sets (combinations of areas the adversary must visit to cause radiological sabotage) and the candidate vital area sets (combinations of areas that must be protected against adversary access to prevent radiological sabotage). Any one of the candidate vital area sets can be selected for protection. Appropriate selection criteria will allow the licensee or new reactor applicant to minimize the impacts of vital area protection measures on plant safety, cost, operations, or other factors of concern.

  9. New radiological material detection technologies for nuclear forensics: Remote optical imaging and graphene-based sensors.

    SciTech Connect (OSTI)

    Harrison, Richard Karl; Martin, Jeffrey B.; Wiemann, Dora K.; Choi, Junoh; Howell, Stephen W.

    2015-09-01

    We developed new detector technologies to identify the presence of radioactive materials for nuclear forensics applications. First, we investigated an optical radiation detection technique based on imaging nitrogen fluorescence excited by ionizing radiation. We demonstrated optical detection in air under indoor and outdoor conditions for alpha particles and gamma radiation at distances up to 75 meters. We also contributed to the development of next generation systems and concepts that could enable remote detection at distances greater than 1 km, and originated a concept that could enable daytime operation of the technique. A second area of research was the development of room-temperature graphene-based sensors for radiation detection and measurement. In this project, we observed tunable optical and charged particle detection, and developed improved devices. With further development, the advancements described in this report could enable new capabilities for nuclear forensics applications.

  10. Validation of reference materials for uranium radiochronometry in the frame of nuclear forensic investigations

    SciTech Connect (OSTI)

    Varga, Z.; Mayer, K.; Bonamici, C. E.; Hubert, A.; Hutcheon, I.; Kinman, W.; Kristo, M.; Pointurier, F.; Spencer, K.; Stanley, F.; Steiner, R.; Tandon, L.; Williams, R.

    2015-05-11

    The results of a joint effort by expert nuclear forensic laboratories in the area of age dating of uranium, i.e. the elapsed time since the last chemical purification of the material are presented and discussed. Completely separated uranium materials of known production date were distributed among the laboratories, and the samples were dated according to routine laboratory procedures by the measurement of the ²²⁰Th/²³⁴U ratio. The measurement results were in good agreement with the known production date showing that the concept for preparing uranium age dating reference material based on complete separation is valid. Detailed knowledge of the laboratory procedures used for uranium age dating allows the identification of possible improvements in the current protocols and the development of improved practice in the future. The availability of age dating reference materials as well as the evolvement of the age dating best-practice protocol will increase the relevance and applicability of age dating as part of the tool-kit available for nuclear forensic investigations.

  11. Validation of reference materials for uranium radiochronometry in the frame of nuclear forensic investigations

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Varga, Z.; Mayer, K.; Bonamici, C. E.; Hubert, A.; Hutcheon, I.; Kinman, W.; Kristo, M.; Pointurier, F.; Spencer, K.; Stanley, F.; et al

    2015-05-11

    The results of a joint effort by expert nuclear forensic laboratories in the area of age dating of uranium, i.e. the elapsed time since the last chemical purification of the material are presented and discussed. Completely separated uranium materials of known production date were distributed among the laboratories, and the samples were dated according to routine laboratory procedures by the measurement of the ²²⁰Th/²³⁴U ratio. The measurement results were in good agreement with the known production date showing that the concept for preparing uranium age dating reference material based on complete separation is valid. Detailed knowledge of the laboratory proceduresmore » used for uranium age dating allows the identification of possible improvements in the current protocols and the development of improved practice in the future. The availability of age dating reference materials as well as the evolvement of the age dating best-practice protocol will increase the relevance and applicability of age dating as part of the tool-kit available for nuclear forensic investigations.« less

  12. Materials and Sensor R&D to Transform the Nuclear Stockpile: Livermore?s

    Office of Scientific and Technical Information (OSTI)

    Transformational Materials Initiative (Technical Report) | SciTech Connect Materials and Sensor R&D to Transform the Nuclear Stockpile: Livermore?s Transformational Materials Initiative Citation Details In-Document Search Title: Materials and Sensor R&D to Transform the Nuclear Stockpile: Livermore?s Transformational Materials Initiative × You are accessing a document from the Department of Energy's (DOE) SciTech Connect. This site is a product of DOE's Office of Scientific and

  13. ENVIRONMENTALMONITORING REPORT FORTRENRVADATEST SITE AND OTRER TEST AREAS USED FOR UNDERGROUND NUCLEAR DEZONATIONS

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ENVIRONMENTALMONITORING REPORT FORTRENRVADATEST SITE AND OTRER TEST AREAS USED FOR UNDERGROUND NUCLEAR DEZONATIONS ' January-December 1972 This work performed under a Memorandum of yi- "h \ -;, Understanding No. AT(26-l)-539. ', * ,",', for the , .; \: , *t a' '_. U. S. ATOMIC ENERGY COMMISSION .-I < . . J c-c I NERC-LV-539-23 ENVIRONMENTAL MONITORING REPORT FOR THE NEVADA TEST SITE AND OTHER TEST AREAS USED FOR UNDERGROUND NUCLEAR DETONATIONS January-December 1972 by the National

  14. DOE-STD-1183-2004; Nuclear Safety Specialist Functional Area Qualification Standard

    Office of Environmental Management (EM)

    DOE-STD-1183-2004 April 2004 DOE STANDARD NUCLEAR SAFETY SPECIALIST FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. DOE-STD-1183-2004 ii This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of

  15. DOE-STD-1185-2004; Nuclear Explosive Safety Study Functional Area Qualification Standard

    Office of Environmental Management (EM)

    STD-1185-2004 August 2004 DOE STANDARD NUCLEAR EXPLOSIVE SAFETY STUDY FUNCTIONAL AREA QUALIFICATION STANDARD DOE Defense Nuclear Facilities Technical Personnel U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE DOE-STD-1185-2004 i This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information

  16. First time nuclear material detection by one short-pulse-laser-driven

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    neutron source Science & Innovation » Technical Articles » First time nuclear material detection by one short-pulse-laser-driven neutron source First time nuclear material detection by one short-pulse-laser-driven neutron source The results obtained are the first experimental demonstration of active interrogation of nuclear material by a short pulse laser driven neutron source. April 3, 2013 TRIDENT pulse The results obtained are the first experimental demonstration of active

  17. U.S. and UAE Bolster Cooperation in the Area of Nuclear Energy and

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Nonproliferation | Department of Energy Bolster Cooperation in the Area of Nuclear Energy and Nonproliferation U.S. and UAE Bolster Cooperation in the Area of Nuclear Energy and Nonproliferation February 24, 2010 - 12:00am Addthis ABU DHABI - As part of a trip to strengthen partnerships in the Middle East, today U.S. Energy Secretary Steven Chu signed an Implementing Arrangement on peaceful uses of nuclear energy with the United Arab Emirates' Minister of State for Foreign Affairs, Dr. Anwar

  18. U.S., Kazakhstan Agree to Areas of Cooperation in Civil Nuclear Energy |

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Department of Energy , Kazakhstan Agree to Areas of Cooperation in Civil Nuclear Energy U.S., Kazakhstan Agree to Areas of Cooperation in Civil Nuclear Energy July 14, 2010 - 11:42am Addthis At their meeting in Astana on July 13, Ed McGinnis, Deputy Assistant Secretary for International Nuclear Energy Policy and Cooperation of the U.S. Department of Energy, and Albert Rau, First Vice Minister of Kazakhstan's Ministry of Industry and New Technologies, signed the Terms of Reference for the

  19. Nuclear Materials Research and Technology/Los Alamos National...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    In the early 1990s, a Russian team at the Joint Institute of Nuclear Re- search at Dubna ... In this experimental setup, nuclear reaction products re- coil out of the thin 233 U ...

  20. Controlling WMD Materials and Expertise | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

  1. Nuclear Materials Safeguards and Security Upgrade Project | National

    National Nuclear Security Administration (NNSA)

    Nuclear Security Administration | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery Jobs Apply for Our Jobs Our

  2. Materials Physics and Applications Division Lead | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration Physics and Applications Division Lead | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery

  3. Materials Science: the science of everything | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration Science: the science of everything | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery Jobs Apply

  4. Evaluation of MC&A Effectiveness and Its Contribution to the Safeguarding Of Nuclear Material with Assurance Assessments

    SciTech Connect (OSTI)

    Schlegel, Steven C.

    2007-07-10

    Safeguards and Security within the DOE complex has struggled with integrating MC&A and Physical Security together in a single model. Attempts were made to incorporate MC&A elements that provide detection into vulnerability assessments. While this approach has met with some success, it does not fully address the different contributions that each make to nuclear material protection. Protection measures that rely on the lack of alarms to imply all nuclear material is still present, in the correct location, and intended use are limited due to their passive nature. A highly effective system may provide confidence that all nuclear material is still present, but it does not provide assurance that it is there. MC&A, through active measures that confirm or verify the actual presence of nuclear material, provides assurance that all of the nuclear material is controlled and accounted for. This paper presents a model that combines the detection and assessment functions from vulnerability assessments with assurance activities provided by MC&A to provide an integrated model that can be used for evaluation of current systems, evaluation of system changes, and monitoring assurance in real time based upon operational activities. 1.0 OVERVIEW Material control and accounting (MC&A) and physical security provide complementary measures that can effectively protect nuclear material against the threats of theft, diversion, and sabotage. Tools have been introduced to evaluate and quantify the effectiveness of different protective measures and schemes, but the ability to fully model the contribution of MC&A to protection effectiveness has been limited. This is due, in part, by not fully recognizing that the two areas contribute differently, but not independently, to protection effectiveness. Physical protection provides detection, assessment, interruption, neutralization, and deterrence against a threat. Except for deterrence, mathematical models have been developed to quantify the contributions of the other elements to obtain an effectiveness value. MC&A helps contribute to this model by providing some detection capabilities and providing assessment under some circumstances to ensure all of the nuclear material is still present as documented. A strong program provides great confidence that nuclear material remains in the location and amounts documented in the nuclear material accounting system. Physical protection is not perfect, however, necessitating MC&A contribution.

  5. The Science of Nuclear Materials: A Modular, Laboratory-based Curriculum

    SciTech Connect (OSTI)

    Cahill, C.L.; Feldman, G.; Briscoe, W.J.

    2014-06-15

    The development of a curriculum for nuclear materials courses targeting students pursuing Master of Arts degrees at The George Washington University is described. The courses include basic concepts such as radiation and radioactivity as well as more complex topics such the nuclear fuel cycle, nuclear weapons, radiation detection and technological aspects of non-proliferation.

  6. Material Disposal Area G Clean-up Overview and Status | Department of

    Office of Environmental Management (EM)

    Energy Material Disposal Area G Clean-up Overview and Status Material Disposal Area G Clean-up Overview and Status Topic: Jeff Mousseau LANL, Provided Information on the Strategy for Closing of Technical Area 54 MDA G. Information Included the Process for Site Characterization, Remediation and the Path Forward. PDF icon MDA G Closure - January 29, 2014 More Documents & Publications Overview of Environmental Programs Proposed Process: NNMCAB Input on Campaigns Associate Directorate for

  7. Literature survey of blast and fire effects of nuclear weapons on urban areas

    SciTech Connect (OSTI)

    Reitter, T.A.; McCallen, D.B.; Kang, S.W.

    1982-06-01

    The American literature of the past 30 years on fire and blast effects of nuclear weapons on urban areas has been surveyed. The relevant work is briefly sketched and areas where information is apparently lacking are noted. This report is intended to provide the basis for suggesting research priorities in the fire and blast effects area for the Federal Emergency Management Agency. It is also intended to provide entry into the literature for researchers. over 850 references are given.

  8. Conference on Advances in Materials Science | National Nuclear Security

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Administration | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Countering Nuclear Terrorism About Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Library Bios Congressional Testimony Fact Sheets Newsletters Press Releases Photo Gallery Jobs Apply for Our Jobs Our Jobs Working at NNSA

  9. Office of Material Management and Minimization | National Nuclear...

    National Nuclear Security Administration (NNSA)

    honored two NNSA Removes U.S.-Origin HEU from Jamaica, Makes the Caribbean HEU Free WASHINGTON, D.C. - The Department of Energy's National Nuclear Security Administration ...

  10. Areas for US-India civilian nuclear cooperation to prevent/mitigate radiological events.

    SciTech Connect (OSTI)

    Balachandran, Gopalan; Forden, Geoffrey Ethan

    2013-01-01

    Over the decades, India and the United States have had very little formal collaboration on nuclear issues. Partly this was because neither country needed collaboration to make progress in the nuclear field. But it was also due, in part, to the concerns both countries had about the other's intentions. Now that the U.S.-India Deal on nuclear collaboration has been signed and the Hyde Act passed in the United States, it is possible to recognize that both countries can benefit from such nuclear collaboration, especially if it starts with issues important to both countries that do not touch on strategic systems. Fortunately, there are many noncontroversial areas for collaboration. This study, funded by the U.S. State Department, has identified a number of areas in the prevention of and response to radiological incidents where such collaboration could take place.

  11. Overview on backfill materials and permeable reactive barriers for nuclear waste disposal facilities.

    SciTech Connect (OSTI)

    Moore, Robert Charles; Hasan, Ahmed Ali Mohamed; Holt, Kathleen Caroline; Hasan, Mahmoud A.

    2003-10-01

    A great deal of money and effort has been spent on environmental restoration during the past several decades. Significant progress has been made on improving air quality, cleaning up and preventing leaching from dumps and landfills, and improving surface water quality. However, significant challenges still exist in all of these areas. Among the more difficult and expensive environmental problems, and often the primary factor limiting closure of contaminated sites following surface restoration, is contamination of ground water. The most common technology used for remediating ground water is surface treatment where the water is pumped to the surface, treated and pumped back into the ground or released at a nearby river or lake. Although still useful for certain remediation scenarios, the limitations of pump-and-treat technologies have recently been recognized, along with the need for innovative solutions to ground-water contamination. Even with the current challenges we face there is a strong need to create geological repository systems for dispose of radioactive wastes containing long-lived radionuclides. The potential contamination of groundwater is a major factor in selection of a radioactive waste disposal site, design of the facility, future scenarios such as human intrusion into the repository and possible need for retrieving the radioactive material, and the use of backfills designed to keep the radionuclides immobile. One of the most promising technologies for remediation of contaminated sites and design of radioactive waste repositories is the use of permeable reactive barriers (PRBs). PRBs are constructed of reactive material(s) to intercept and remove the radionuclides from the water and decontaminate the plumes in situ. The concept of PRBs is relatively simple. The reactive material(s) is placed in the subsurface between the waste or contaminated area and the groundwater. Reactive materials used thus far in practice and research include zero valent iron, hydroxyapatite, magnesium oxide, and others. As the contaminant moves through the reactive material, the contaminant is either sorbed by the reactive material or chemically reacts with the material to form a less harmful substance. Because of the high risk associated with failure of a geological repository for nuclear waste, most nations favor a near-field multibarrier engineered system using backfill materials to prevent release of radionuclides into the surrounding groundwater.

  12. INFORMATION: Inspection Report on "Removal of Categories I and II Special Nuclear Material from Sandia National Laboratories-New Mexico"

    SciTech Connect (OSTI)

    2010-01-01

    The Department of Energy's (DOE's) Sandia National Laboratories-New Mexico (Sandia) develops science-based technologies in support of national security in areas such as nuclear weapons, nonproliferation, military technologies, and homeland security. Sandia's primary mission is ensuring that the U.S. nuclear arsenal is safe, secure, and reliable and can fully support the Nation's deterrence policy. Part of this mission includes systems engineering of nuclear weapons; research, design, and development of non-nuclear components; manufacturing of non-nuclear weapons components; the provision of safety, security, and reliability assessments of stockpile weapons; and the conduct of high-explosives research and development and environmental testing. Sandia Corporation, a subsidiary of Lockheed Martin Corporation, operates Sandia for the National Nuclear Security Administration (NNSA). On May 7, 2004, the Secretary announced that the Department would evaluate missions at DOE sites to consolidate Special Nuclear Material (SNM) in the most secure environments possible. The Administrator of the NNSA said that this effort was a key part of an overall plan to transform the nuclear weapons complex into a smaller, safer, more secure, and more efficient national security enterprise. In February 2008, Sandia was the first site to report it had reduced its on-site inventory of nuclear material below 'Categories I and II' levels, which require the highest level of security to protect material such as plutonium and highly enriched uranium. The Office of Inspector General initiated an inspection to determine if Sandia made appropriate adjustments to its security posture in response to the removal of the Categories I and II SNM. We found that Sandia adjusted its security posture in response to the removal of Categories I and II SNM. For example, security posts were closed; unneeded protective force weapons and equipment were excessed from the site; and, Sandia's Site Safeguards and Security Plan was modified. We also found that some highly enriched uranium in a complex material configuration was not removed from Sandia. This material was designated as Category III material using a methodology for assessing the attractiveness of complex materials that was not specifically addressed in any current DOE directive. Although DOE and NNSA officials believed that this designation was appropriate, the methodology used to support this designation had not, as of the time of our review, been incorporated into the DOE directives system. Historically, the Department has considered the categorization of SNM to be an important national security and public policy issue. Consequently, we believe that expedited action should be taken to formalize this methodology in the DOE directives system and that it be disseminated throughout the Department of Energy complex.

  13. Nuclear Material Control and Accountability (NMC&A) for the Savannah River

    Office of Environmental Management (EM)

    Site Tritium Facilities | Department of Energy Material Control and Accountability (NMC&A) for the Savannah River Site Tritium Facilities Nuclear Material Control and Accountability (NMC&A) for the Savannah River Site Tritium Facilities Presentation from the 35th Tritium Focus Group Meeting held in Princeton, New Jersey on May 05-07, 2015. PDF icon Nuclear Material Control and Accountability (NMC&A) for the Savannah River Site Tritium Facilities More Documents & Publications

  14. Office of Global Material Security | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    National Nuclear Security Administration (DOENNSA) and the U.K. Department of Energy and Climate Change concluded a workshop at Wilton Park, About This Site Budget IG Web Policy...

  15. Detecting special nuclear materials in containers using high-energy gamma rays emitted by fission products

    DOE Patents [OSTI]

    Norman, Eric B.; Prussin, Stanley G.

    2007-10-02

    A method and a system for detecting the presence of special nuclear materials in a container. The system and its method include irradiating the container with an energetic beam, so as to induce a fission in the special nuclear materials, detecting the gamma rays that are emitted from the fission products formed by the fission, to produce a detector signal, comparing the detector signal with a threshold value to form a comparison, and detecting the presence of the special nuclear materials using the comparison.

  16. Transformational, Large Area Fabrication of Nanostructured Materials Using Plasma Arc Lamps

    SciTech Connect (OSTI)

    2009-03-01

    This factsheet describes a study that will address critical additional steps over large areas of as-synthesized nanostructured materials, such as annealing, phase transformation, or activation of dopants, dramatically reducing the processing costs of the solid-state lighting and photovoltaic materials.

  17. Heat resistant materials and their feasibility issues for a space nuclear transportation system

    SciTech Connect (OSTI)

    Olsen, C.S.

    1991-01-01

    A number of nuclear propulsion concepts based on solid-core nuclear propulsion are being evaluated for a nuclear propulsion transportation system to support the Space Exploration Initiative (SEI) involving the reestablishment of a manned lunar base and the subsequent exploration of Mars. These systems will require high-temperature materials to meet the operating conditions with appropriate reliability and safety built into these systems through the selection and testing of appropriate materials. The application of materials for nuclear thermal propulsion (NTP) and nuclear electric propulsion (NEP) systems and the feasibility issues identified for their use will be discussed. Some mechanical property measurements have been obtained, and compatibility tests were conducted to help identify feasibility issues. 3 refs., 1 fig., 4 tabs.

  18. Novel Methods of Tritium Sequestration: High Temperature Gettering and Separation Membrane Materials Discovery for Nuclear Energy Systems

    SciTech Connect (OSTI)

    Chen, Franglin; Sholl, David; Brinkman, Kyle; Lyer, Ratnasabapathy; Reifsnider, Kenneth

    2015-01-22

    This project is aimed at addressing critical issues related to tritium sequestration in next generation nuclear energy systems. A technical hurdle to the use of high temperature heat from the exhaust produced in the next generation nuclear processes in commercial applications such as nuclear hydrogen production is the trace level of tritium present in the exhaust gas streams. This presents a significant challenge since the removal of tritium from the high temperature gas stream must be accomplished at elevated temperatures in order to subsequently make use of this heat in downstream processing. One aspect of the current project is to extend the techniques and knowledge base for metal hydride materials being developed for the ''hydrogen economy'' based on low temperature absorption/desorption of hydrogen to develop materials with adequate thermal stability and an affinity for hydrogen at elevated temperatures. The second focus area of this project is to evaluate high temperature proton conducting materials as hydrogen isotope separation membranes. Both computational and experimental approaches will be applied to enhance the knowledge base of hydrogen interactions with metal and metal oxide materials. The common theme between both branches of research is the emphasis on both composition and microstructure influence on the performance of sequestration materials.

  19. Next Generation Nuclear Plant Materials Selection and Qualification Program Plan

    SciTech Connect (OSTI)

    R. Doug Hamelin; G. O. Hayner

    2004-11-01

    The U.S. Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design is a graphite-moderated, helium-cooled, prismatic or pebble bed thermal neutron spectrum reactor with an average reactor outlet temperature of at least 1000 C. The NGNP will use very high burn up, lowenriched uranium, TRISO-Coated fuel in a once-through fuel cycle. The design service life of the NGNP is 60 years.

  20. Next Generation Nuclear Plant Materials Research and Development Program Plan

    SciTech Connect (OSTI)

    G. O. Hayner; E.L. Shaber

    2004-09-01

    The U.S Department of Energy (DOE) has selected the Very High Temperature Reactor (VHTR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production without greenhouse gas emissions. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed, thermal neutron spectrum reactor that will produce electricity and hydrogen in a state-of-the-art thermodynamically efficient manner. The NGNP will use very high burn-up, low-enriched uranium, TRISO-coated fuel and have a projected plant design service life of 60 years.

  1. THE ATTRACTIVENESS OF MATERIALS IN ADVANCED NUCLEAR FUEL CYCLES FOR VARIOUS PROLIFERATION AND THEFT SCENARIOS

    SciTech Connect (OSTI)

    Bathke, C. G.; Ebbinghaus, Bartley B.; Collins, Brian A.; Sleaford, Brad W.; Hase, Kevin R.; Robel, Martin; Wallace, R. K.; Bradley, Keith S.; Ireland, J. R.; Jarvinen, G. D.; Johnson, M. W.; Prichard, Andrew W.; Smith, Brian W.

    2012-08-29

    We must anticipate that the day is approaching when details of nuclear weapons design and fabrication will become common knowledge. On that day we must be particularly certain that all special nuclear materials (SNM) are adequately accounted for and protected and that we have a clear understanding of the utility of nuclear materials to potential adversaries. To this end, this paper examines the attractiveness of materials mixtures containing SNM and alternate nuclear materials associated with the plutonium-uranium reduction extraction (Purex), uranium extraction (UREX), coextraction (COEX), thorium extraction (THOREX), and PYROX (an electrochemical refining method) reprocessing schemes. This paper provides a set of figures of merit for evaluating material attractiveness that covers a broad range of proliferant state and subnational group capabilities. The primary conclusion of this paper is that all fissile material must be rigorously safeguarded to detect diversion by a state and must be provided the highest levels of physical protection to prevent theft by subnational groups; no 'silver bullet' fuel cycle has been found that will permit the relaxation of current international safeguards or national physical security protection levels. The work reported herein has been performed at the request of the U.S. Department of Energy (DOE) and is based on the calculation of 'attractiveness levels' that are expressed in terms consistent with, but normally reserved for, the nuclear materials in DOE nuclear facilities. The methodology and findings are presented. Additionally, how these attractiveness levels relate to proliferation resistance and physical security is discussed.

  2. Implementation Plan and Initial Development of Nuclear Concrete Materials Database for Light Water Reactor Sustainability Program

    Broader source: Energy.gov [DOE]

    The FY10 activities for development of a nuclear concrete materials database to support the Light Water Reactor Sustainability Program are summarized. The database will be designed and constructed...

  3. CONSTRUCTION OF WEB-ACCESSIBLE MATERIALS HANDBOOK FORGENERATION IV NUCLEAR REACTORS

    SciTech Connect (OSTI)

    Ren, Weiju

    2005-01-01

    The development of a web-accessible materials handbook in support of the materials selection and structural design for the Generation IV nuclear reactors is being planned. Background of the reactor program is briefly introduced. Evolution of materials handbooks for nuclear reactors over years is reviewed in light of the trends brought forth by the rapid advancement in information technologies. The framework, major features, contents, and construction considerations of the web-accessible Gen IV Materials Handbook are discussed. Potential further developments and applications of the handbook are also elucidated.

  4. REVIEW OF EQUIPMENT USED IN RUSSIAN PRACTICE FOR ACCOUNTING MEASUREMENTS OF NUCLEAR MATERIALS.

    SciTech Connect (OSTI)

    NEYMOTIN,L.

    1999-07-25

    The objective of this work was to analyze instrumentation and methodologies used at Russian nuclear facilities for measurement of item nuclear materials, materials in bulk form, and waste streams; specify possibilities for the application of accounting measurements; and develop recommendations for improvement. The major steps and results: Representative conversion, enrichment (gas centrifuge), fuel fabrication, spent fuel reprocessing, and chemical-metallurgical production facilities in Russia were selected; Full lists of nuclear materials were prepared; Information about measurement methods and instrumentation for each type of nuclear material were gathered; and Recommendations on methodological and instrumentation support of accounting measurements for all types of materials were formulated. The analysis showed that the existing measurement methods and instrumentation serve mostly to support the technological process control and nuclear and radiation safety control. Requirements for these applications are lower than requirements for MC and A applications. To improve the state of MC and A at Russian nuclear facilities, significant changes in instrumentation support will be required, specifically in weighing equipment, volume measurements, and destructive and non-destructive analysis equipment, along with certified reference materials.

  5. Audit Report on "The Department's Management of Nuclear Materials Provided to Domestic Licensees"

    SciTech Connect (OSTI)

    2009-02-01

    The objective if to determine whether the Department of Energy (Department) was adequately managing its nuclear materials provided to domestic licensees. The audit was performed from February 2007 to September 2008 at Department Headquarters in Washington, DC, and Germantown, MD; the Oak Ridge Office and the Oak Ridge National Laboratory in Oak Ridge, TN. In addition, we visited or obtained data from 40 different non-Departmental facilities in various states. To accomplish the audit objective, we: (1) Reviewed Departmental and Nuclear Regulatory Commission (NRC) requirements for the control and accountability of nuclear materials; (2) Analyzed a Nuclear Materials Management and Safeguards System (NMMSS) report with ending inventory balances for Department-owned nuclear materials dated September 30, 2007, to determine the amount and types of nuclear materials located at non-Department domestic facilities; (3) Held discussions with Department and NRC personnel that used NMMSS information to determine their roles and responsibilities related to the control and accountability over nuclear materials; (4) Selected a judgmental sample of 40 non-Department domestic facilities; (5) Met with licensee officials and sent confirmations to determine whether their actual inventories of Department-owned nuclear materials were consistent with inventories reported in the NMMSS; and, (6) Analyzed historical information related to the 2004 NMMSS inventory rebaselining initiative to determine the quantity of Department-owned nuclear materials that were written off from the domestic licensees inventory balances. This performance audit was conducted in accordance with generally accepted Government auditing standards. Those standards require that we plan and perform the audit to obtain sufficient, appropriate evidence to provide a reasonable basis for our findings and conclusions based on our audit objective. We believe that the evidence obtained provides a reasonable basis for our findings and conclusions based on our audit objectives. The audit included tests of controls and compliance with laws and regulations related to managing the Department-owned nuclear materials provided to non-Departmental domestic licensees. Because our review was limited it would not necessarily have disclosed all internal control deficiencies that may have existed at the time of our audit. We examined the establishment of performance measures in accordance with Government Performance and Results Act of 1993, as they related to the audit objective. We found that the Department had established performance measures related to removing or disposing of nuclear materials and radiological sources around the world. We utilized computer generated data during our audit and performed procedures to validate the reliability of the information as necessary to satisfy our audit objective. As noted in the report, we questioned the reliability of the NMMSS data.

  6. Self assembled molecular monolayers on high surface area materials as molecular getters

    DOE Patents [OSTI]

    King, David E. (Lakewood, CO); Herdt, Gregory C. (Denver, CO); Czanderna, Alvin W. (Denver, CO)

    1997-01-01

    The present invention relates to a gettering material that may be used as a filtration medium to remove pollutants from the environment. The gettering material comprises a high surface area material having a metal surface that chemically bonds n-alkanethiols in an organized manner thereby forming a molecular monolayer over the metal surface. The n-alkanethiols have a free functional group that interacts with the environment thereby binding specific pollutants that may be present. The gettering material may be exposed to streams of air in heating, ventilation, and air conditioning systems or streams of water to remove specific pollutants from either medium.

  7. Self assembled molecular monolayers on high surface area materials as molecular getters

    DOE Patents [OSTI]

    King, D.E.; Herdt, G.C.; Czanderna, A.W.

    1997-01-07

    The present invention relates to a gettering material that may be used as a filtration medium to remove pollutants from the environment. The gettering material comprises a high surface area material having a metal surface that chemically bonds n-alkanethiols in an organized manner thereby forming a molecular monolayer over the metal surface. The n-alkanethiols have a free functional group that interacts with the environment thereby binding specific pollutants that may be present. The gettering material may be exposed to streams of air in heating, ventilation, and air conditioning systems or streams of water to remove specific pollutants from either medium. 9 figs.

  8. Federal Automated Information System of Nuclear Material Control and Accounting: Uniform System of Reporting Documents

    SciTech Connect (OSTI)

    Pitel, M V; Kasumova, L; Babcock, R A; Heinberg, C

    2003-06-12

    One of the fundamental regulations of the Russian State System for Nuclear Material Accounting and Control (SSAC), ''Basic Nuclear Material Control and Accounting Rules,'' directed that a uniform report system be developed to support the operation of the SSAC. According to the ''Regulation on State Nuclear Material Control and Accounting,'' adopted by the Russian Federation Government, Minatom of Russia is response for the development and adoption of report forms, as well as the reporting procedure and schedule. The report forms are being developed in tandem with the creation of an automated national nuclear material control and accounting system, the Federal Information System (FIS). The forms are in different stages of development and implementation. The first report forms (the Summarized Inventory Listing (SIL), Summarized Inventory Change Report (SICR) and federal and agency registers of nuclear material) have already been created and implemented. The second set of reports (nuclear material movement reports and the special anomaly report) is currently in development. A third set of reports (reports on import/export operations, and foreign nuclear material temporarily located in the Russian Federation) is still in the conceptual stage. To facilitate the development of a unified document system, the FIS must establish a uniform philosophy for the reporting system and determine the requirements for each reporting level, adhering to the following principles: completeness--the unified report system provides the entire range of information that the FIS requires to perform SSAC tasks; requisite level of detail; hierarchical structure--each report is based on the information provided in a lower-level report and is the source of information for reports at the next highest level; consistency checking--reports can be checked against other reports. A similar philosophy should eliminate redundancy in the different reports, support a uniform approach to the contents of previously developed and new reports within the FIS, as well as identify the main priorities for the direction of the FIS.

  9. Approved reference and testing materials for use in Nuclear Waste Management Research and Development Programs

    SciTech Connect (OSTI)

    Mellinger, G.B.; Daniel, J.L.

    1984-12-01

    This document, addressed to members of the waste management research and development community summarizes reference and testing materials available from the Nuclear Waste Materials Characterization Center (MCC). These materials are furnished under the MCC's charter to distribute reference materials essential for quantitative evaluation of nuclear waste package materials under development in the US. Reference materials with known behavior in various standard waste management related tests are needed to ensure that individual testing programs are correctly performing those tests. Approved testing materials are provided to assist the projects in assembling materials data base of defensible accuracy and precision. This is the second issue of this publication. Eight new Approved Testing Materials are listed, and Spent Fuel is included as a separate section of Standard Materials because of its increasing importance as a potential repository storage form. A summary of current characterization information is provided for each material listed. Future issues will provide updates of the characterization status of the materials presented in this issue, and information about new standard materials as they are acquired. 7 references, 1 figure, 19 tables.

  10. Development of ion beam techniques for the study of special nuclear materials related problems

    SciTech Connect (OSTI)

    Maggiore, C.J.; Tesmer, J.R.; Martz, J.C.

    1998-11-01

    This is the final report of a three-year, Laboratory Directed Research and Development (LDRD) project at the Los Alamos National Laboratory (LANL). The scientific objective of this project was to develop the ion beam techniques for the characterization of actinides and their effects on other materials. It was designed to enhance their ability to quantitatively understand the oxidation, corrosion, diffusion, stability, and radiation damage of actinides and the materials with which they are in contact. The authors developed and applied several low-energy nuclear techniques (resonant and nonresonant backscattering, nuclear reaction analysis, and particle-induced x-ray emission) to the quantitative study of the near surfaces of actinide and tritide materials, and determined the absolute accuracy and precision of ion beam measurements on these materials. They also demonstrated the use of variable-energy alpha beams for the study of accelerated aging of polymeric materials in contact with actinide materials.

  11. Nuclear Materials Technology Division/Los Alamos National Laboratory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Los Alamos National Laboratory * A U.S. Department of Energy Laboratory The Actinide Research o f t h e N u c l e a r M a t e r i a l s T e c h n o l o g y D i v i s i o n Quarterly In This Issue 1 High-gradient Magnetic Separation (HGMS) Plays an Important Role in Radioactive Waste Remediation 4 Researchers Invent Novel Plutonium- Selective Anion Exchange Resins for Waste Minimization 6 LDRD Funds Seven Research Areas in NMT 7 NMT Researchers Nurture the Year-Old Actinide Research Quarterly 8

  12. Cladding and Structural Materials for Advanced Nuclear Energy Systems

    SciTech Connect (OSTI)

    Was, G S; Allen, T R; Ila, D; C,; Levi,; Morgan, D; Motta, A; Wang, L; Wirth, B

    2011-06-30

    The goal of this consortium is to address key materials issues in the most promising advanced reactor concepts that have yet to be resolved or that are beyond the existing experience base of dose or burnup. The research program consists of three major thrusts: 1) high-dose radiation stability of advanced fast reactor fuel cladding alloys, 2) irradiation creep at high temperature, and 3) innovative cladding concepts embodying functionally-graded barrier materials. This NERI-Consortium final report represents the collective efforts of a large number of individuals over a period of three and a half years and included 9 PIs, 4 scientists, 3 post-docs and 12 students from the seven participating institutions and 8 partners from 5 national laboratories and 3 industrial institutions (see table). University participants met semi-annually and participants and partners met annually for meetings lasting 2-3 days and designed to disseminate and discuss results, update partners, address outstanding issues and maintain focus and direction toward achieving the objectives of the program. The participants felt that this was a highly successful program to address broader issues that can only be done by the assembly of a range of talent and capabilities at a more substantial funding level than the traditional NERI or NEUP grant. As evidence of the success, this group, collectively, has published 20 articles in archival journals and made 57 presentations at international conferences on the results of this consortium.

  13. A Preliminary Evaluation of Using Fill Materials to Stabilize Used Nuclear Fuel During Storage and Transportation

    SciTech Connect (OSTI)

    Maheras, Steven J.; Best, Ralph; Ross, Steven B.; Lahti, Erik A.; Richmond, David J.

    2012-08-01

    This report contains a preliminary evaluation of potential fill materials that could be used to fill void spaces in and around used nuclear fuel contained in dry storage canisters in order to stabilize the geometry and mechanical structure of the used nuclear fuel during extended storage and transportation after extended storage. Previous work is summarized, conceptual descriptions of how canisters might be filled were developed, and requirements for potential fill materials were developed. Elements of the requirements included criticality avoidance, heat transfer or thermodynamic properties, homogeneity and rheological properties, retrievability, material availability and cost, weight and radiation shielding, and operational considerations. Potential fill materials were grouped into 5 categories and their properties, advantages, disadvantages, and requirements for future testing were discussed. The categories were molten materials, which included molten metals and paraffin; particulates and beads; resins; foams; and grout. Based on this analysis, further development of fill materials to stabilize used nuclear fuel during storage and transportation is not recommended unless options such as showing that the fuel remains intact or canning of used nuclear fuel do not prove to be feasible.

  14. Interoperability of Materials Database Systems in Support of Nuclear Energy Development and Potential Applications for Fuel Cell Material Selection

    SciTech Connect (OSTI)

    Lin, Lianshan; Austin, Timothy; Ren, Weiju

    2015-01-01

    Materials database interoperability has been of great interest in recent years for information exchange in support of research and development (R&D). In response to data and knowledge sharing needs of the GenIV International Forum (GIF) for global collaboration in nuclear energy R&D, the European Commission JRC Institute for Energy and Transport (JRC-IET) and the Oak Ridge National Laboratory (ORNL) have established a materials database interoperability project that develops techniques for automated materials data exchange between systems hosted at the two institutes MatDB Online at JRC IET and the Gen IV Materials Handbook at ORNL, respectively. The work to enable automated exchange of data between the two systems leverages the XML data import and export functionalities of both systems in combination with recently developed standards for engineering materials data. The preliminary results of data communication between the two systems have demonstrated the feasibility and efficiency of materials database interoperability, which constructs an interoperation framework that can be seamlessly integrated into the high-throughput First Principles material databases and thus advance the discovery of novel materials in fuel cell applications.

  15. Interoperability of Materials Database Systems in Support of Nuclear Energy Development and Potential Applications for Fuel Cell Material Selection

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Lin, Lianshan; Austin, Timothy; Ren, Weiju

    2015-01-01

    Materials database interoperability has been of great interest in recent years for information exchange in support of research and development (R&D). In response to data and knowledge sharing needs of the GenIV International Forum (GIF) for global collaboration in nuclear energy R&D, the European Commission JRC Institute for Energy and Transport (JRC-IET) and the Oak Ridge National Laboratory (ORNL) have established a materials database interoperability project that develops techniques for automated materials data exchange between systems hosted at the two institutes MatDB Online at JRC IET and the Gen IV Materials Handbook at ORNL, respectively. The work to enable automatedmoreexchange of data between the two systems leverages the XML data import and export functionalities of both systems in combination with recently developed standards for engineering materials data. The preliminary results of data communication between the two systems have demonstrated the feasibility and efficiency of materials database interoperability, which constructs an interoperation framework that can be seamlessly integrated into the high-throughput First Principles material databases and thus advance the discovery of novel materials in fuel cell applications.less

  16. Cultural Resource Investigations for the Resumption of Transient Testing of Nuclear Fuels and Material at the Idaho National Laboratory

    SciTech Connect (OSTI)

    Brenda R. Pace; Julie B. Williams

    2013-11-01

    The U. S. Department of Energy (DOE) has a need to test nuclear fuels under conditions that subject them to short bursts of intense, high-power radiation called transient testing in order to gain important information necessary for licensing new nuclear fuels for use in U.S. nuclear power plants, for developing information to help improve current nuclear power plant performance and sustainability, for improving the affordability of new generation reactors, for developing recyclable nuclear fuels, and for developing fuels that inhibit any repurposing into nuclear weapons. To meet this mission need, DOE is considering alternatives for re-use and modification of existing nuclear reactor facilities to support a renewed transient testing program. One alternative under consideration involves restarting the Transient Reactor Test (TREAT) reactor located at the Materials and Fuels Complex (MFC) on the Idaho National Laboratory (INL) site in southeastern Idaho. This report summarizes cultural resource investigations conducted by the INL Cultural Resource Management Office in 2013 to support environmental review of activities associated with restarting the TREAT reactor at the INL. These investigations were completed in order to identify and assess the significance of cultural resources within areas of potential effect associated with the proposed action and determine if the TREAT alternative would affect significant cultural resources or historic properties that are eligible for nomination to the National Register of Historic Places. No archaeological resources were identified in the direct area of potential effects for the project, but four of the buildings proposed for modifications are evaluated as historic properties, potentially eligible for nomination to the National Register of Historic Places. This includes the TREAT reactor (building #), control building (building #), guardhouse (building #), and warehouse (building #). The proposed re-use of these historic properties is consistent with original missions related to nuclear reactor testing and is expected to result in no adverse effects to their historic significance. Cultural resource investigations also involved communication with representatives from the Shoshone-Bannock Tribes to characterize cultural resources of potential tribal concern. This report provides a summary of the cultural resources inventoried and assessed within the defined areas of potential effect for the resumption of transient testing at the INL. Based on these analyses, proposed activities would have no adverse effects on historic properties within the APEs that have been defined. Other archaeological resources and cultural resources of potential concern to the Shoshone-Bannock Tribes and others that are located near the APEs are also discussed with regard to potential indirect impacts. The report concludes with general recommendations for measures to reduce impacts to all identified resources.

  17. UNITED STATES ATOMIC ENERGY COMMISSION SPECIAL NUCLEAR MATERIAL LlCENSE

    Office of Legacy Management (LM)

    ' ,' ' .:,: ' ,' ,,.. : .-: .: .A,.. :. .:,: ' .' :l:. ,:.:,. ,. ."i i..' ./. ' . : :, *:..: ,.a~ :.. ,::;: ;#j ,,. .,.' ' : 8:;) ,,> ,' UNITED STATES ATOMIC ENERGY COMMISSION SPECIAL NUCLEAR MATERIAL LlCENSE pp.o-o\ 43 Licensee 1. Name spm%r ch+ti (hlqay 3. 2. Address i%si&t Building Kansas cay 5, ifissouri ~..--. 3. License No. .m4-329 I 4. Exp/rotion Date Sepikmber 30, I.962 -6. Special Nuclear:Material ~~~~SnrichedtoS~ I under this license ia the a-235 i.soto~p. one thoti (1ooo)

  18. Comparison of preparation techniques for nuclear materials for transmission electron microscopy (TEM)

    SciTech Connect (OSTI)

    Aitkaliyeva, Assel; Madden, James W.; Miller, Brandon D; Cole, James I; Gan, Jian

    2015-04-01

    Preparation of highly radioactive and irradiated nuclear fuels and materials for transmission electron microscopy (TEM) is conjoined with a set of unique challenges, including but not limited to personnel radiation exposure and contamination. The paper evaluates three specimen preparation techniques for preparation of irradiated materials and determines which technique yields to the most reliable characterization of radiation damage microstructure. Various specimen preparation artifacts associated with each technique are considered and ways of minimizing these artifacts are addressed.

  19. EIS-0220: Interim Management of Nuclear Materials at the Savannah River Site

    Broader source: Energy.gov [DOE]

    This environmental impact statement assesses the potential environmental impacts of actions necessary to manage nuclear materials at the Savannah River Site (SRS) in Aiken, South Carolina, until decisions on their ultimate disposition are made and implemented. The Department of Energy has decided to initiate actions which will stabilize certain of the SRS materials that represent environment, safety and health vulnerabilities in their current storage condition or which may represent a vulnerability within the next 10 years.

  20. Supporting the Global Threat Reduction Initiative through Nuclear Material Recovery: Collaboration between NNSA and AREVA

    SciTech Connect (OSTI)

    Bieniawski, Andrew; Sheely, Ken; Hunter, Ian; Louvet, Thibault

    2007-07-01

    The Global Threat Reduction Initiative (GTRI) was established by the U.S. Department of Energy National Nuclear Security Administration (NNSA) in response to the growing need to comprehensively and internationally address the potential threat posed by vulnerable high-risk nuclear material. GTRI's mission is to foster international support for national programs to identify, secure, remove and/or facilitate the disposition, as quickly and expeditiously as possible, of vulnerable, high-risk nuclear and other radioactive materials around the world that pose a potential threat to the international community. Specifically, GTRI establishes international partnerships to address this global issue. To achieve these objectives, GTRI works with international, regional, and domestic partners to: (1) minimize and, to the extent possible, eliminate the use of highly enriched uranium (HEU) in civil nuclear applications worldwide by converting research reactors to LEU fuels; (2) accelerate the removal or final disposition of vulnerable nuclear material throughout the world; (3) accelerate securing and/or removing vulnerable high-risk radiological materials throughout the world; and (4) address the 'gaps' of other programs by identifying throughout the world, recovering and facilitating permanent disposition of vulnerable high-risk nuclear material not previously addressed by other threat reduction programs. DOE desires to work with more partners, both government and industry, to develop options for the disposal of nuclear material in the most expeditious manner. This paper will present the recent success of the first Plutonium Gap Material recycling contract signed by AREVA thanks to the collaboration developed between NNSA and AREVA. Another item which will be presented and illustrates how GTRI supports government-to-industry partnership, is the willingness to consider the treatment option for Gap Materials used-fuel. This new step represents another broadening of the collaboration that already exists between NNSA and AREVA for achieving the goal of GTRI. Such collaboration was already illustrated in 2006 by the recovery of more than 45 Kg of HEU from facilities within Europe and another 15 Kg of fresh HEU were transported from Europe to the U.S. An additional 40 Kg of fresh HEU will be transported from facilities within Europe to the AREVA-CERCA facility before the end of 2007. (authors)

  1. Material Development for Tooling Applications Using Big Area Additive Manufacturing (BAAM)

    SciTech Connect (OSTI)

    Duty, Chad E.; Drye, Tom; Franc, Alan

    2015-03-01

    Techmer Engineered Solutions (TES) is working with Oak Ridge National Laboratory (ORNL) to develop materials and evaluate their use for ORNL s recently developed Big Area Additive Manufacturing (BAAM) system for tooling applications. The first phase of the project established the performance of some commercially available polymer compositions deposited with the BAAM system. Carbon fiber reinforced ABS demonstrated a tensile strength of nearly 10 ksi, which is sufficient for a number of low temperature tooling applications.

  2. Energy Frontier Research Center, Center for Materials Science of Nuclear Fuels

    SciTech Connect (OSTI)

    Todd R. Allen

    2011-12-01

    This is a document required by Basic Energy Sciences as part of a mid-term review, in the third year of the five-year award period and is intended to provide a critical assessment of the Center for Materials Science of Nuclear Fuels (strategic vision, scientific plans and progress, and technical accomplishments).

  3. Special nuclear materials cutoff exercise: Issues and lessons learned, Volume 2 of 3: Appendixes A - C

    SciTech Connect (OSTI)

    Libby, R.A.; Davis, C.; Segal, J.E.; Stanbro, W.D.

    1995-08-01

    This document is the 2nd volume of the three volume set from the Special Nuclear Materials Cutoff Exercise held at Hanford in 1994. Volume 2 contains Appendices A-C, with Appendices A and B containing a discussion of the design of the PUREX process and Appendix C containing a discussion of the safeguards measures for the PUREX facility.

  4. Competing effects of electronic and nuclear energy loss on microstructural evolution in ionic-covalent materials

    SciTech Connect (OSTI)

    Zhang, Yanwen; Varga, Tamas; Ishimaru, Dr. Manabu; Edmondson, Dr. Philip; Xue, Haizhou; Liu, Peng; Moll, Sandra; Namavar, Fereydoon; Hardiman, Chris; Shannon, Prof. Steven; Weber, William J

    2014-01-01

    Ever increasing energy needs have raised the demands for advanced fuels and cladding materials that withstand the extreme radiation environments with improved accident tolerance over a long period of time. Ceria (CeO2) is a well known ionic conductor that is isostructural with urania and plutonia-based nuclear fuels. In the context of nuclear fuels, immobilization and transmutation of actinides, CeO2 is a model system for radiation effect studies. Covalent silicon carbide (SiC) is a candidate for use as structural material in fusion, cladding material for fission reactors, and an inert matrix for the transmutation of plutonium and other radioactive actinides. Understanding microstructural change of these ionic-covalent materials to irradiation is important for advanced nuclear energy systems. While displacements from nuclear energy loss may be the primary contribution to damage accumulation in a crystalline matrix and a driving force for the grain boundary evolution in nanostructured materials, local non-equilibrium disorder and excitation through electronic energy loss may, however, produce additional damage or anneal pre-existing defect. At intermediate transit energies where electronic and nuclear energy losses are both significant, synergistic, additive or competitive processes may evolve that affect the dynamic response of materials to irradiation. The response of crystalline and nanostructured CeO2 and SiC to ion irradiation are studied under different nuclear and electronic stopping powers to describe some general material response in this transit energy regime. Although fast radiation-induced grain growth in CeO2 is evident with no phase transformation, different fluence and dose dependence on the growth rate is observed under Si and Au irradiations. While grain shrinkage and amorphization are observed in the nano-engineered 3C SiC with a high-density of stacking faults embedded in nanosize columnar grains, significantly enhanced radiation resistance is attributed to stacking faults that promote efficient point defect annihilation. Moreover, competing effects of electronic and nuclear energy loss on the damage accumulation and annihilation are observed in crystalline 4H-SiC. Systematic experiments and simulation effort are needed to understand the competitive or synergistic effects.

  5. 105-K Basin Material Design Basis Feed Description for Spent Nuclear Fuel (SNF) Project Facilities VOL 1 Fuel

    SciTech Connect (OSTI)

    PACKER, M.J.

    1999-11-04

    Metallic uranium Spent Nuclear Fuel (SNF) is currently stored within two water filled pools, 105-KE Basin (KE Basin) and 105-KW Basin (KW Basin), at the United States Department of Energy (U.S. DOE) Hanford Site, in southeastern Washington State. The Spent Nuclear Fuel Project (SNF Project) is responsible to DOE for operation of these fuel storage pools and for the 2100 metric tons of SNF materials that they contain. The SNF Project mission includes safe removal and transportation of all SNF from these storage basins to a new storage facility in the 200 East Area. To accomplish this mission, the SNF Project modifies the existing KE Basin and KW Basin facilities and constructs two new facilities: the 100 K Area Cold Vacuum Drying Facility (CVDF), which drains and dries the SNF; and the 200 East Area Canister Storage Building (CSB), which stores the SNF. The purpose of this document is to describe the design basis feed compositions for materials stored or processed by SNF Project facilities and activities. This document is not intended to replace the Hanford Spent Fuel Inventory Baseline (WHC 1994b), but only to supplement it by providing more detail on the chemical and radiological inventories in the fuel (this volume) and sludge. A variety of feed definitions is required to support evaluation of specific facility and process considerations during the development of these new facilities. Six separate feed types have been identified for development of new storage or processing facilities. The approach for using each feed during design evaluations is to calculate the proposed facility flowsheet assuming each feed. The process flowsheet would then provide a basis for material compositions and quantities which are used in follow-on calculations.

  6. Nuclear Safety Information Agreement Between the U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, and the U.S. Department of Energy, Office of Environment, Health, Safety and Security

    Broader source: Energy.gov [DOE]

    On December 15, Matt Moury, Associate Under Secretary, Office of Environment, Health, Safety and Security (EHSS DOE) and EHSS Office of Nuclear Safety staff met with the NRC Executive Director for Operations, the Deputy Executive Director for Operations, and the Director, Office of Nuclear Materials Safety and Safeguards to sign a nuclear safety information exchange agreement between NRC Office of Nuclear Materials Safety and Safeguards and the Office of Environment, Health, Safety and Security.

  7. Advanced international training course on state systems of accounting for and control of nuclear materials

    SciTech Connect (OSTI)

    Not Available

    1981-10-01

    This report incorporates all lectures and presentations at the Advanced International Training Course on State Systems of Accounting for and Control of Nuclear Material held April 27 through May 12, 1981 at Santa Fe and Los Alamos, New Mexico, and Richland, Washington, USA. Authorized by the US Nuclear Non-Proliferation Act and sponsored by the US Department of Energy in cooperation with the International Atomic Energy Agency, the course was developed to provide practical training in the design, implementation, and operation of a state system of nuclear materials accountability and control that satisfies both national and international safeguards. Major emphasis for the 1981 course was placed on safeguards methods used at bulk-handling facilities, particularly low-enriched uranium conversion and fuel fabrication plants. The course was conducted by the University of California's Los Alamos National Laboratory, the Battelle Pacific Northwest Laboratory, and Exxon Nuclear Company, Inc. Tours and demonstrations were arranged at both the Los Alamos National Laboratory, Los Alamos, New Mexico, and the Exxon Nuclear fuel fabrication plant, Richland, Washington.

  8. Recent Fast Neutron Imaging Measurements with the Fieldable Nuclear Materials Identification System

    SciTech Connect (OSTI)

    Wellington, Tracey; Palles, Blake A; Mullens, James Allen; Mihalczo, John T; Archer, Daniel E; Thompson, Thad; Britton Jr, Charles L; Ezell, N Dianne Bull; Ericson, Milton Nance; Farquhar, Ethan; Lind, Randall F; Carter, Jake

    2015-01-01

    This paper describes some recent fast neutron imaging measurements of the fieldable nuclear materials identification system (FNMIS) under development by the National Nuclear Security Administration (NNSA-NA-22) for possible future use in arms control and nonproliferation applications. The general configuration of FNMIS has been previously described, and a description of the application-specific integrated circuit (ASIC) electronics designed for FNMIS has been reported. This paper presents initial imaging measurements performed at ORNL with a Thermo Fisher API 120 DT generator and the fast-neutron imaging module of FNMIS.

  9. Novel Processing of Unique Ceramic-Based Nuclear Materials and Fuels

    SciTech Connect (OSTI)

    Hui Zhang; Raman P. Singh

    2008-11-30

    Advances in nuclear reactor technology and the use of gas-cooled fast reactors require the development of new materials that can operate at the higher temperatures expected in these systems. These include refractory alloys base on Nb, Zr, Ta, Mo, W, and Re; ceramics and composites such as those based on silicon carbide (SiCf-SiC); carbon-carbon composites; and advanced coatings. Besides the ability to handle higher expected temperatures, effective heat transfer between reactor componets is necessary for improved efficiency. Improving thermal conductivity of the materials used in nuclear fuels and other temperature critical components can lower the center-line fuel temperature and thereby enhance durability and reduce the risk of premature failure.

  10. Electrorefiner system for recovering purified metal from impure nuclear feed material

    DOE Patents [OSTI]

    Berger, John F.; Williamson, Mark A.; Wiedmeyer, Stanley G.; Willit, James L.; Barnes, Laurel A.; Blaskovitz, Robert J.

    2015-10-06

    An electrorefiner system according to a non-limiting embodiment of the present invention may include a vessel configured to maintain a molten salt electrolyte and configured to receive a plurality of alternately arranged cathode and anode assemblies. The anode assemblies are configured to hold an impure nuclear feed material. Upon application of the power system, the impure nuclear feed material is anodically dissolved and a purified metal is deposited on the cathode rods of the cathode assemblies. A scraper is configured to dislodge the purified metal deposited on the cathode rods. A conveyor system is disposed at a bottom of the vessel and configured to remove the dislodged purified metal from the vessel.

  11. Nuclear power plant containment metallic pressure boundary materials and plans for collecting and presenting their properties

    SciTech Connect (OSTI)

    Oland, C.B.

    1995-04-01

    A program is being conducted at the Oak Ridge National Laboratory (ORNL to assist the Nuclear Regulatory Commission (NRC)) in their assessment of the effects of degradation (primarily corrosion) on the structural capacity and leaktight integrity of metal containments and steel liners of reinforced concrete structures in nuclear power plants. One of the program objectives is to characterize and quantify manifestations of corrosion on the properties of steels used to construct containment pressure boundary components. This report describes a plan for use in collecting and presenting data and information on ferrous alloys permitted for use in construction of pressure retaining components in concrete and metal containments. Discussions about various degradation mechanisms that could potentially affect the mechanical properties of these materials are also included. Conclusions and recommendations presented in this report will be used to guide the collection of data and information that will be used to prepare a material properties data base for containment steels.

  12. Production of an English/Russian glossary of terminology for nuclear materials control and accounting

    SciTech Connect (OSTI)

    Schachowskoj, S.; Smith, H.A. Jr.

    1995-05-01

    The program plans for Former Soviet Union National Nuclear Materials Control and Accounting (MC and A) Systems Enhancements call for the development of an English/Russian Glossary of MC and A terminology. This glossary was envisioned as an outgrowth of the many interactions, training sessions, and other talking and writing exercises that would transpire in the course of carrying out these programs. This report summarizes the status of the production of this glossary, the most recent copy of which is attached to this report. The glossary contains over 950 terms and acronyms associated with nuclear material control and accounting for safeguards and nonproliferation. This document is organized as follows: English/Russian glossary of terms and acronyms; Russian/English glossary of terms and acronyms; English/Russian glossary of acronyms; and Russian/English glossary of acronyms.

  13. United States-Russian laboratory-to-laboratory cooperation on protection, control, and accounting for naval nuclear materials

    SciTech Connect (OSTI)

    Sukhoruchkin, V.; Yurasov, N.; Goncharenko, Y.; Mullen, M.; McConnell, D.

    1996-12-31

    In March 1995, the Russian Navy contacted safeguards experts at the Kurchatov Institute (KI) and proposed the initiation of work to enhance nuclear materials protection, control, and accounting (MPC and A) at Russian Navy facilities. Because of KI`s successful experience in laboratory-to-laboratory MPC and A cooperation with US Department of Energy Laboratories, the possibility of US participation in the work with the Russian Navy was explored. Several months later, approval was received from the US Government and the Russian Navy to proceed with this work on a laboratory-to-laboratory basis through Kurchatov Institute. As a first step in the cooperation, a planning meeting occurred at KI in September, 1995. Representatives from the US Department of Energy (DOE), the US Department of Defense (DOD), the Russian Navy, and KI discussed several areas for near-term cooperative work, including a vulnerability assessment workshop and a planning study to identify and prioritize near-term MPC and A enhancements that might be implemented at Russian facilities which store or handle unirradiated highly enriched uranium fuel for naval propulsion applications. In subsequent meetings, these early proposals have been further refined and extended. This MPC and A cooperation will now include enhanced protection and control features for storage facilities and refueling service ships, computerized accounting systems for naval fuel, methods and equipment for rapid inventories, improved security of fresh fuel during truck transportation, and training. This paper describes the current status and future plans for MPC and A cooperation for naval nuclear materials.

  14. DOE-STD-1071-94; DOE Standard Guideline to Good Practices for Material Receipt, Inspection, Handling, Storage, Retrieval, and Issuance at DOE Nuclear Facilities

    Office of Environmental Management (EM)

    71-94 June 1994 DOE STANDARD GUIDELINE TO GOOD PRACTICES FOR MATERIAL RECEIPT, INSPECTION, HANDLING, STORAGE, RETRIEVAL, AND ISSUANCE AT DOE NUCLEAR FACILITIES U.S. Department of Energy AREA MNTY Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from the Office of Scientific and Technical Information, P.O. Box 62, Oak Ridge, TN

  15. Rev 8 NEVADA NATIONAL SECURITY SITE - WASTE RIS VAB ACCOUNTABLE NUCLEAR MATERIALS

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    7/14 Rev 8 NEVADA NATIONAL SECURITY SITE - WASTE RIS VAB ACCOUNTABLE NUCLEAR MATERIALS AUTHORIZATION TO SHIP WASTE Return To: Date: NNSS Material Control and Accountability Program (NMR@nv.doe.gov) David Klamann: 702-295-7872 Laura Harris: 702-295-3760 Mary Alice Price: 702-295-4812 Fax No.: 702-295-4215 Waste Shipment #: 741#: Anticipated Arrival Week: Waste Generator Org & Address: Waste Generator Point of Contact: Phone: Fax: Please use the column that applies to your site. DOE M 470.4-6

  16. INFCIRC/207 - Notification to the Agency of Exports and Imports of Nuclear Material

    National Nuclear Security Administration (NNSA)

    INF INFCIRC/207 26 July 1974 International Atomic Energy Agency INFORMATION CIRCULAR GENERAL Distr. Original: ENGLISH and RUSSIAN NOTIFICATION TO THE AGENCY OF EXPORTS AND IMPORTS OF NUCLEAR MATERIAL On 11 July 1974 the Director General received letters dated 10 July from the Resident Representatives to the Agency of the Union of Soviet Socialist Republics, the United Kingdom of Great Britain and Northern Ireland and the United States of America informing him that in the interest of assisting

  17. Los Alamos National Laboratory new generation standard nuclear material storage container - the SAVY4000 design

    SciTech Connect (OSTI)

    Stone, Timothy Amos

    2010-01-01

    Incidents involving release of nuclear materials stored in containers of convenience such as food pack cans, slip lid taped cans, paint cans, etc. has resulted in defense board concerns over the lack of prescriptive performance requirements for interim storage of nuclear materials. Los Alamos National Laboratory (LANL) has shared in these incidents and in response proactively moved into developing a performance based standard involving storage of nuclear material (RD003). This RD003 requirements document has sense been updated to reflect requirements as identified with recently issued DOE M 441.1-1 'Nuclear Material Packaging Manual'. The new packaging manual was issued at the encouragement of the Defense Nuclear Facilities Safety Board with a clear directive for protecting the worker from exposure due to loss of containment of stored materials. The Manual specifies a detailed and all inclusive approach to achieve a high level of protection; from package design & performance requirements, design life determinations of limited life components, authorized contents evaluations, and surveillance/maintenance to ensure in use package integrity over time. Materials in scope involve those stored outside an approved engineered-contamination barrier that would result in a worker exposure of in excess of 5 rem Committed Effective Does Equivalent (CEDE). Key aspects of meeting the challenge as developed around the SAVY-3000 vented storage container design will be discussed. Design performance and acceptance criteria against the manual, bounding conditions as established that the user must ensure are met to authorize contents in the package (based upon the activity of heat-source plutonium (90% Pu-238) oxide, which bounds the requirements for weapons-grade plutonium oxide), interface as a safety class system within the facility under the LANL plutonium facility DSA, design life determinations for limited life components, and a sense of design specific surveillance program implementation as LANL moves forward into production and use of the SAVY-3000 will all be addressed. The SAVY-3000 is intended as a work horse package for the DOE complex as a vented storage container primarily for plutonium in solid form.

  18. Reliability of emerging bonded interface materials for large-area attachments

    SciTech Connect (OSTI)

    Paret, Paul P.; DeVoto, Douglas J.; Narumanchi, Sreekant

    2015-12-30

    In this study, conventional thermal interface materials (TIMs), such as greases, gels, and phase change materials, pose bottlenecks to heat removal and have long caused reliability issues in automotive power electronics packages. Bonded interface materials (BIMs) with superior thermal performance have the potential to be a replacement to the conventional TIMs. However, due to coefficient of thermal expansion mismatches between different components in a package and resultant thermomechanical stresses, fractures or delamination could occur, causing serious reliability concerns. These defects manifest themselves in increased thermal resistance in the package. In this paper, the results of reliability evaluation of emerging BIMs for large-area attachments in power electronics packaging are reported. Thermoplastic (polyamide) adhesive with embedded near-vertical-aligned carbon fibers, sintered silver, and conventional lead solder (Sn63Pb37) materials were bonded between 50.8 mm x 50.8 mm cross-sectional footprint silicon nitride substrates and copper base plate samples, and were subjected to accelerated thermal cycling until failure or 2500 cycles. Damage in the BIMs was monitored every 100 cycles by scanning acoustic microscopy. Thermoplastic with embedded carbon fibers performed the best with no defects, whereas sintered silver and lead solder failed at 2300 and 1400 thermal cycles, respectively. Besides thermal cycling, additional lead solder samples were subjected to thermal shock and thermal cycling with extended dwell periods. A finite element method (FEM)-based model was developed to simulate the behavior of lead solder under thermomechanical loading. Strain energy density per cycle results were calculated from the FEM simulations. A predictive lifetime model was formulated for lead solder by correlating strain energy density results extracted from modeling with cycles-to-failure obtained from experimental accelerated tests. A power-law-based approach was used to formulate the - redictive lifetime model.

  19. Reliability of emerging bonded interface materials for large-area attachments

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Paret, Paul P.; DeVoto, Douglas J.; Narumanchi, Sreekant

    2015-12-30

    In this study, conventional thermal interface materials (TIMs), such as greases, gels, and phase change materials, pose bottlenecks to heat removal and have long caused reliability issues in automotive power electronics packages. Bonded interface materials (BIMs) with superior thermal performance have the potential to be a replacement to the conventional TIMs. However, due to coefficient of thermal expansion mismatches between different components in a package and resultant thermomechanical stresses, fractures or delamination could occur, causing serious reliability concerns. These defects manifest themselves in increased thermal resistance in the package. In this paper, the results of reliability evaluation of emerging BIMsmore » for large-area attachments in power electronics packaging are reported. Thermoplastic (polyamide) adhesive with embedded near-vertical-aligned carbon fibers, sintered silver, and conventional lead solder (Sn63Pb37) materials were bonded between 50.8 mm x 50.8 mm cross-sectional footprint silicon nitride substrates and copper base plate samples, and were subjected to accelerated thermal cycling until failure or 2500 cycles. Damage in the BIMs was monitored every 100 cycles by scanning acoustic microscopy. Thermoplastic with embedded carbon fibers performed the best with no defects, whereas sintered silver and lead solder failed at 2300 and 1400 thermal cycles, respectively. Besides thermal cycling, additional lead solder samples were subjected to thermal shock and thermal cycling with extended dwell periods. A finite element method (FEM)-based model was developed to simulate the behavior of lead solder under thermomechanical loading. Strain energy density per cycle results were calculated from the FEM simulations. A predictive lifetime model was formulated for lead solder by correlating strain energy density results extracted from modeling with cycles-to-failure obtained from experimental accelerated tests. A power-law-based approach was used to formulate the - redictive lifetime model.« less

  20. Detecting special nuclear materials in suspect containers using high-energy gamma rays emitted by fission products

    DOE Patents [OSTI]

    Norman, Eric B.; Prussin, Stanley G.

    2009-01-27

    A method and a system for detecting the presence of special nuclear materials in a suspect container. The system and its method include irradiating the suspect container with a beam of neutrons, so as to induce a thermal fission in a portion of the special nuclear materials, detecting the gamma rays that are emitted from the fission products formed by the thermal fission, to produce a detector signal, comparing the detector signal with a threshold value to form a comparison, and detecting the presence of the special nuclear materials using the comparison.

  1. Detecting special nuclear materials in suspect containers using high-energy gamma rays emitted by fission products

    DOE Patents [OSTI]

    Norman, Eric B [Oakland, CA; Prussin, Stanley G [Kensington, CA

    2009-05-05

    A method and a system for detecting the presence of special nuclear materials in a suspect container. The system and its method include irradiating the suspect container with a beam of neutrons, so as to induce a thermal fission in a portion of the special nuclear materials, detecting the gamma rays that are emitted from the fission products formed by the thermal fission, to produce a detector signal, comparing the detector signal with a threshold value to form a comparison, and detecting the presence of the special nuclear materials using the comparison.

  2. Detecting special nuclear materials in suspect containers using high-energy gamma rays emitted by fission products

    DOE Patents [OSTI]

    Norman, Eric B.; Prussin, Stanley G.

    2009-01-06

    A method and a system for detecting the presence of special nuclear materials in a suspect container. The system and its method include irradiating the suspect container with a beam of neutrons, so as to induce a thermal fission in a portion of the special nuclear materials, detecting the gamma rays that are emitted from the fission products formed by the thermal fission, to produce a detector signal, comparing the detector signal with a threshold value to form a comparison, and detecting the presence of the special nuclear materials using the comparison.

  3. Evaluating Safeguards Benefits of Process Monitoring as compared with Nuclear Material Accountancy

    SciTech Connect (OSTI)

    Humberto Garcia; Wen-Chiao Lin; Reed Carlson

    2014-07-01

    This paper illustrates potential safeguards benefits that process monitoring (PM) may have as a diversion deterrent and as a complementary safeguards measure to nuclear material accountancy (NMA). This benefit is illustrated by quantifying the standard deviation associated with detecting a considered material diversion scenario using either an NMA-based method or a PM-based approach. To illustrate the benefits of PM for effective safeguards, we consider a reprocessing facility. We assume that the diversion of interest for detection manifests itself as a loss of Pu caused by abnormally operating a dissolver for an extended period to accomplish protracted diversion (or misdirection) of Pu to a retained (unconditioned) waste stream. For detecting the occurrence of this diversion (which involves anomalous operation of the dissolver), we consider two different data evaluation and integration (DEI) approaches, one based on NMA and the other based on PM. The approach based on PM does not directly do mass balance calculations, but rather monitors for the possible occurrence of anomaly patterns related to potential loss of nuclear material. It is thus assumed that the loss of a given mass amount of nuclear material can be directly associated with the execution of proliferation-driven activities that trigger the occurrence of an anomaly pattern consisting of series of events or signatures occurring at different unit operations and time instances. By effectively assessing these events over time and space, the PM-based DEI approach tries to infer whether this specific pattern of events has occurred and how many times within a given time period. To evaluate the goodness of PM, the 3 Sigma of the estimated mass loss is computed under both DEI approaches as function of the number of input batches processed. Simulation results are discussed.

  4. Uncertainty quantification in application of the enrichment meter principle for nondestructive assay of special nuclear material

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Burr, Tom; Croft, Stephen; Jarman, Kenneth D.

    2015-09-05

    The various methods of nondestructive assay (NDA) of special nuclear material (SNM) have applications in nuclear nonproliferation, including detection and identification of illicit SNM at border crossings, and quantifying SNM at nuclear facilities for safeguards. No assay method is complete without “error bars,” which provide one way of expressing confidence in the assay result. Consequently, NDA specialists typically quantify total uncertainty in terms of “random” and “systematic” components, and then specify error bars for the total mass estimate in multiple items. Uncertainty quantification (UQ) for NDA has always been important, but it is recognized that greater rigor is needed andmore » achievable using modern statistical methods. To this end, we describe the extent to which the guideline for expressing uncertainty in measurements (GUM) can be used for NDA. Also, we propose improvements over GUM for NDA by illustrating UQ challenges that it does not address, including calibration with errors in predictors, model error, and item-specific biases. A case study is presented using low-resolution NaI spectra and applying the enrichment meter principle to estimate the U-235 mass in an item. The case study illustrates how to update the current American Society for Testing and Materials guide for application of the enrichment meter principle using gamma spectra from a NaI detector.« less

  5. Uncertainty quantification in application of the enrichment meter principle for nondestructive assay of special nuclear material

    SciTech Connect (OSTI)

    Burr, Tom; Croft, Stephen; Jarman, Kenneth D.

    2015-09-05

    The various methods of nondestructive assay (NDA) of special nuclear material (SNM) have applications in nuclear nonproliferation, including detection and identification of illicit SNM at border crossings, and quantifying SNM at nuclear facilities for safeguards. No assay method is complete without error bars, which provide one way of expressing confidence in the assay result. Consequently, NDA specialists typically quantify total uncertainty in terms of random and systematic components, and then specify error bars for the total mass estimate in multiple items. Uncertainty quantification (UQ) for NDA has always been important, but it is recognized that greater rigor is needed and achievable using modern statistical methods. To this end, we describe the extent to which the guideline for expressing uncertainty in measurements (GUM) can be used for NDA. Also, we propose improvements over GUM for NDA by illustrating UQ challenges that it does not address, including calibration with errors in predictors, model error, and item-specific biases. A case study is presented using low-resolution NaI spectra and applying the enrichment meter principle to estimate the U-235 mass in an item. The case study illustrates how to update the current American Society for Testing and Materials guide for application of the enrichment meter principle using gamma spectra from a NaI detector.

  6. Microsoft PowerPoint - Nuclear Material Import Export License … Uses & Reporting processes_Gary Langlie_Karen Antizzo [Compatib

    National Nuclear Security Administration (NNSA)

    Material Import/Export License - Uses & Reporting processes Gary Langlie - Nuclear Regulatory Commission Karen Antizzo - Link Technologies Overview  What is a Nuclear Regulatory Commission (NRC) import/export license? - Licenses for imports - Licenses for exports - Export license monitoring  Highlights of imports/exports in 2014 - Nuclear material imported to the U.S. - Nuclear material exported from the U.S. - Types of materials shipped - Typical uses and applications  What is

  7. Offsite environmental monitoring report: Radiation monitoring around United States nuclear test areas, calendar year 1991

    SciTech Connect (OSTI)

    Chaloud, D.J.; Dicey, B.B.; Mullen, A.A.; Neale, A.C.; Sparks, A.R.; Fontana, C.A.; Carroll, L.D.; Phillips, W.G.; Smith, D.D.; Thome, D.J.

    1992-01-01

    This report describes the Offsite Radiation Safety Program conducted during 1991 by the Environmental Protection Agency`s (EPA`s) Environmental Monitoring Systems Laboratory-Las Vegas. This laboratory operates an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether current radiation levels and associated doses to the general public are in compliance with existing radiation protection standards. The surveillance program additionally has the responsibility to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling milk, water, and air; by deploying thermoluminescent dosimeters (TLDs) and using pressurized ion chambers (PICs); and by biological monitoring of animals, food crops, and humans. Personnel with mobile monitoring equipment are placed in areas downwind from the test site prior to each nuclear weapons test to implement protective actions, provide immediate radiation monitoring, and obtain environmental samples rapidly after any occurrence of radioactivity release. Comparison of the measurements and sample analysis results with background levels and with appropriate standards and regulations indicated that there was no radioactivity detected offsite by the various EPA monitoring networks and no exposure above natural background to the population living in the vicinity of the NTS that could be attributed to current NTS activities. Annual and long-term trends were evaluated in the Noble Gas, Tritium, Milk Surveillance, Biomonitoring, TLD, PIC networks, and the Long-Term Hydrological Monitoring Program.

  8. Next Generation Nuclear Plant Steam Generator and Intermediate Heat Exchanger Materials Research and Development Plan

    SciTech Connect (OSTI)

    J. K. Wright

    2010-09-01

    DOE has selected the High Temperature Gas-cooled Reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production. It will have an outlet gas temperature in the range of 900°C and a plant design service life of 60 years. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed reactor and use low-enriched uranium, Tri-Isotopic (TRISO)-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Today’s high-temperature alloys and associated ASME Codes for reactor applications are approved up to 760°C. However, some primary system components, such as the Intermediate Heat Exchanger (IHX) for the NGNP will require use of materials that can withstand higher temperatures. The thermal, environmental, and service life conditions of the NGNP will make selection and qualification of some high-temperature materials a significant challenge. Examples include materials for the core barrel and core internals, such as the control rod sleeves. The requirements of the materials for the IHX are among the most demanding. Selection of the technology and design configuration for the NGNP must consider both the cost and risk profiles to ensure that the demonstration plant establishes a sound foundation for future commercial deployments. The NGNP challenge is to achieve a significant advancement in nuclear technology while at the same time setting the stage for an economically viable deployment of the new technology in the commercial sector soon after 2020. A number of solid solution strengthened nickel based alloys have been considered for application in heat exchangers and core internals for the NGNP. The primary candidates are Inconel 617, Haynes 230, Incoloy 800H and Hastelloy XR. Based on the technical maturity, availability in required product forms, experience base, and high temperature mechanical properties all of the vendor pre-conceptual design studies have specified Alloy 617 as the material of choice for heat exchangers. Also a draft code case for Alloy 617 was developed previously. Although action was suspended before the code case was accepted by ASME, this draft code case provides a significant head start for achieving codification of the material. Similarly, Alloy 800H is the material of choice for control rod sleeves. In addition to the above listed considerations, Alloy 800H is already listed in the nuclear section of the ASME Code; although the maximum use temperature and time need to be increased.

  9. Next Generation Nuclear Plant Intermediate Heat Exchanger Materials Research and Development Plan (PLN-2804)

    SciTech Connect (OSTI)

    J. K. Wright

    2008-04-01

    DOE has selected the High Temperature Gas-cooled Reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production. It will have an outlet gas temperature in the range of 900°C and a plant design service life of 60 years. The reactor design will be a graphite moderated, helium-cooled, prismatic or pebble-bed reactor and use low-enriched uranium, Tri-Isotopic (TRISO)-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Materials Research and Development (R&D) Program is responsible for performing R&D on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Today’s high-temperature alloys and associated ASME Codes for reactor applications are approved up to 760°C. However, some primary system components, such as the Intermediate Heat Exchanger (IHX) for the NGNP will require use of materials that can withstand higher temperatures. The thermal, environmental, and service life conditions of the NGNP will make selection and qualification of some high-temperature materials a significant challenge. Examples include materials for the core barrel and core internals, such as the control rod sleeves. The requirements of the materials for the IHX are among the most demanding. Selection of the technology and design configuration for the NGNP must consider both the cost and risk profiles to ensure that the demonstration plant establishes a sound foundation for future commercial deployments. The NGNP challenge is to achieve a significant advancement in nuclear technology while at the same time setting the stage for an economically viable deployment of the new technology in the commercial sector soon after 2020. A number of solid solution strengthened nickel based alloys have been considered for application in heat exchangers and core internals for the NGNP. The primary candidates are Inconel 617, Haynes 230, Incoloy 800H and Hastelloy XR. Based on the technical maturity, availability in required product forms, experience base, and high temperature mechanical properties all of the vendor pre-conceptual design studies have specified Alloy 617 as the material of choice for heat exchangers. Also a draft code case for Alloy 617 was developed previously. Although action was suspended before the code case was accepted by ASME, this draft code case provides a significant head start for achieving codification of the material. Similarly, Alloy 800H is the material of choice for control rod sleeves. In addition to the above listed considerations, Alloy 800H is already listed in the nuclear section of the ASME Code; although the maximum use temperature and time need to be increased.

  10. Compact Detection System for High Sensitivity Hydrogen Profiling of Materials by Nuclear Reaction Analysis

    SciTech Connect (OSTI)

    Marble, Daniel Keith; Urban, Ben; Pacheco, Jose

    2009-03-10

    Hydrogen is a ubiquitous contaminant that is known to have dramatic effects on the electrical, chemical, and mechanical properties of many types of materials in even minute quantities. Thus, the detection of hydrogen in materials is of major importance. Nuclear Reaction Analysis (NRA) is a powerful technique for nondestructive profiling hydrogen in materials. However, NRA has found only limited use in many applications because of poor sensitivity due to cosmic ray background (CSRB). Most attempts to eliminate CSRB to achieve ppm detection levels using higher energy nuclear reactions or tons of passive shielding are not compatible with commercial ion beam analysis space and equipment requirements Zimmerman, et al. have previously reported upon a coincidence detector that meets IBA space requirements and reduces the cosmic ray background, but the detector suffers from lower detection efficiency and small sample size. We have replaced the BGO well detector in the Zimmerman coincidence detection scheme with a larger Nal well detector and used faster timing electronics to produce a detector that can handle larger samples with higher detection efficiency, and still eliminate cosmic ray background.

  11. Implementation of focused ion beam (FIB) system in characterization of nuclear fuels and materials

    SciTech Connect (OSTI)

    A. Aitkaliyeva; J. W. Madden; B. D. Miller; J I Cole; T A Hyde

    2014-10-01

    Beginning in 2007, a program was established at the Idaho National Laboratory to update key capabilities enabling microstructural and micro-chemical characterization of highly irradiated and/or radiologically contaminated nuclear fuels and materials at scales that previously had not been achieved for these types of materials. Such materials typically cannot be contact handled and pose unique hazards to instrument operators, facilities, and associated personnel. One of the first instruments to be acquired was a Dual Beam focused ion beam (FIB)-scanning electron microscope (SEM) to support preparation of transmission electron microscopy and atom probe tomography samples. Over the ensuing years, techniques have been developed and operational experience gained that has enabled significant advancement in the ability to characterize a variety of fuel types including metallic, ceramic, and coated particle fuels, obtaining insights into in-reactor degradation phenomena not obtainable by any other means. The following article describes insights gained, challenges encountered, and provides examples of unique results obtained in adapting Dual Beam FIB technology to nuclear fuels characterization.

  12. US-Russian Cooperation in Upgrading MC&A System at Rosatom Facilities: Measurement of Nuclear Materials

    SciTech Connect (OSTI)

    Powell, Danny H; Jensen, Bruce A

    2011-01-01

    Improve protection of weapons-usable nuclear material from theft or diversion through the development and support of a nationwide sustainable and effective Material Control and Accountability (MC&A) program based on material measurement. The material protection, control, and accountability (MPC&A) cooperation has yielded significant results in implementing MC&A measurements at Russian nuclear facilities: (1) Establishment of MEM WG and MEMS SP; (2) Infrastructure for development, certification, and distribution of RMs; and (3) Coordination on development and implementation of MMs.

  13. Audit Report - The Department of Energy's Management of Surplus Nuclear Materials, OAS-L-13-04

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Management of Surplus Nuclear Materials OAS-L-13-04 January 2013 MEMORANDUM FOR THE DIRECTOR INTEGRATION ADMINISTRATION FROM: Daniel M. Weeber Assistant Inspector General for Audits and Administration Office of Inspector General SUBJECT: INFORMATION Management of Surplus Nuclear Materials BACKGROUND A primary mission of the Department of Energy design, build and test the Nation' Department's complex was devoted to the production and fabrication of n components. With the end of the C suspended or

  14. Business Ymwet Centlsaem: Enclosed is AEC Special Nuclear Material License Yo. SW-551, as

    Office of Legacy Management (LM)

    c-ii 3-y !WL?DF!i 70.424 SW-551, 9s renewed AUG 9 196s cmhustian En&merin~, Inc. %.lelcar Division tYindter, Connecticut ,~ttentionr ?tr. 5. ff. Shfp,penbmg: Business Ymwet Centlsaem: Enclosed is AEC Special Nuclear Material License Yo. SW-551, as renewed. Very tTuly yours, fkmald A. Nusshauaer, Chief Saurce 4 Specfel Wcleer Yaterials Brmch Ofvision of Meterbls Licensing EnClOSUWl W W m , as renwed DISTRIBUTION: Ccaplianee, HQs 2 w/encl. H. j. McAlduff, OR00 w/encl. D. George, ?MM w/mcl. N.

  15. ADMINISTRATIVE CHANGE TO DOE O 474.2, NUCLEAR MATERIAL CONTROL AND ACCOUNTABILITY

    National Nuclear Security Administration (NNSA)

    O 474.2 Chg 1 8-3-11 ADMINISTRATIVE CHANGE TO DOE O 474.2, NUCLEAR MATERIAL CONTROL AND ACCOUNTABILITY LOCATION OF CHANGES: Page Paragraph Changed To 11 6.b. DOE O 470.4A, Safeguards and Security Program, dated 5-25-07 DOE O 470.4B, Safeguards and Security Program, dated 7-21-11 11 6.c. DOE M 470.4-1 Chg 2, Safeguards and Security Program Planning and Management, dated 10-20-11 deleted 11 6.d. DOE M 470.4-2A, Physical Protection, dated 6-29-11 DOE O 473.3, Protection Program Operations, dated

  16. Conceptual design report: Nuclear materials storage facility renovation. Part 5, Structural/seismic investigation. Section A report, existing conditions calculations/supporting information

    SciTech Connect (OSTI)

    1995-07-14

    The Nuclear Materials Storage Facility (NMSF) at the Los Alamos National Laboratory (LANL) was a Fiscal Year (FY) 1984 line-item project completed in 1987 that has never been operated because of major design and construction deficiencies. This renovation project, which will correct those deficiencies and allow operation of the facility, is proposed as an FY 97 line item. The mission of the project is to provide centralized intermediate and long-term storage of special nuclear materials (SNM) associated with defined LANL programmatic missions and to establish a centralized SNM shipping and receiving location for Technical Area (TA)-55 at LANL. Based on current projections, existing storage space for SNM at other locations at LANL will be loaded to capacity by approximately 2002. This will adversely affect LANUs ability to meet its mission requirements in the future. The affected missions include LANL`s weapons research, development, and testing (WRD&T) program; special materials recovery; stockpile survelliance/evaluation; advanced fuels and heat sources development and production; and safe, secure storage of existing nuclear materials inventories. The problem is further exacerbated by LANL`s inability to ship any materials offsite because of the lack of receiver sites for mate rial and regulatory issues. Correction of the current deficiencies and enhancement of the facility will provide centralized storage close to a nuclear materials processing facility. The project will enable long-term, cost-effective storage in a secure environment with reduced radiation exposure to workers, and eliminate potential exposures to the public. Based upon US Department of Energy (DOE) Albuquerque Operations (DOE/Al) Office and LANL projections, storage space limitations/restrictions will begin to affect LANL`s ability to meet its missions between 1998 and 2002.

  17. In-Situ Radiological Surveys to Address Nuclear Criticality Safety Requirements During Remediation Activities at the Shallow Land Disposal Area, Armstrong County, Pennsylvania - 12268

    SciTech Connect (OSTI)

    Norris, Phillip; Mihalo, Mark; Eberlin, John; Lambert, Mike; Matthews, Brian

    2012-07-01

    Cabrera Services Inc. (CABRERA) is the remedial contractor for the Shallow Land Disposal Area (SLDA) Site in Armstrong County Pennsylvania, a United States (US) Army Corps of Engineers - Buffalo District (USACE) contract. The remediation is being completed under the USACE's Formerly Utilized Sites Remedial Action Program (FUSRAP) which was established to identify, investigate, and clean up or control sites previously used by the Atomic Energy Commission (AEC) and its predecessor, the Manhattan Engineer District (MED). As part of the management of the FUSRAP, the USACE is overseeing investigation and remediation of radiological contamination at the SLDA Site in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), 42 US Code (USC), Section 9601 et. seq, as amended and, the National Oil and Hazardous Substance Pollution Contingency Plan (NCP), Title 40 of the Code of Federal Regulations (CFR) Section 300.430(f) (2). The objective of this project is to clean up radioactive waste at SLDA. The radioactive waste contains special nuclear material (SNM), primarily U-235, in 10 burial trenches, Cabrera duties include processing, packaging and transporting the waste to an offsite disposal facility in accordance with the selected remedial alternative as defined in the Final Record of Decision (USACE, 2007). Of particular importance during the remediation is the need to address nuclear criticality safety (NCS) controls for the safe exhumation and management of waste containing fissile materials. The partnership between Cabrera Services, Inc. and Measutronics Corporation led to the development of a valuable survey tool and operating procedure that are essential components of the SLDA Criticality Safety and Material Control and Accountability programs. Using proven existing technologies in the design and manufacture of the Mobile Survey Cart, the continued deployment of the Cart will allow for an efficient and reliable methodology to allow for the safe exhumation of the Special Nuclear Material in existing SLDA trenches. (authors)

  18. Material brittle fracture owing to thermoelastic effect of high energy nuclear particle

    SciTech Connect (OSTI)

    Kalinichenko, A.I.

    1996-12-31

    Rapid arising of the overheated domain near very heavy ion path (near fast neutron collision point) in solid results in generation of cylinder (spherical) thermoelastic stress wave. The latter can exceed the material strength and cause brittle fracture at going out on the free body interface. Size and shape of an erosion zone as well as erosion rate for both sorts of primary nuclear particles are found. The role of wave attenuation is discussed. The products of erosion are of macroscopic scaly particles having the typical thickness (1 {divided_by} 5) {center_dot} 10{sup -7} cm and mass 10{sup -18} {divided_by} 10{sup -17} g. Such ion (neutron)-stimulated thermoacoustic grinding can take place in radioactive materials with fissionable addenda. The consideration of the brittle destruction under cosmic ray bombardment may be essential for equipment of deep space missions.

  19. Terminating Safeguards on Excess Special Nuclear Material: Defense TRU Waste Clean-up and Nonproliferation - 12426

    SciTech Connect (OSTI)

    Hayes, Timothy; Nelson, Roger

    2012-07-01

    The Department of Energy (DOE) and the National Nuclear Security Administration (NNSA) manages defense nuclear material that has been determined to be excess to programmatic needs and declared waste. When these wastes contain plutonium, they almost always meet the definition of defense transuranic (TRU) waste and are thus eligible for disposal at the Waste Isolation Pilot Plant (WIPP). The DOE operates the WIPP in a manner that physical protections for attractiveness level D or higher special nuclear material (SNM) are not the normal operating condition. Therefore, there is currently a requirement to terminate safeguards before disposal of these wastes at the WIPP. Presented are the processes used to terminate safeguards, lessons learned during the termination process, and how these approaches might be useful for future defense TRU waste needing safeguards termination prior to shipment and disposal at the WIPP. Also described is a new criticality control container, which will increase the amount of fissile material that can be loaded per container, and how it will save significant taxpayer dollars. Retrieval, compliant packaging and shipment of retrievably stored legacy TRU waste has dominated disposal operations at WIPP since it began operations 12 years ago. But because most of this legacy waste has successfully been emplaced in WIPP, the TRU waste clean-up focus is turning to newly-generated TRU materials. A major component will be transuranic SNM, currently managed in safeguards-protected vaults around the weapons complex. As DOE and NNSA continue to consolidate and shrink the weapons complex footprint, it is expected that significant quantities of transuranic SNM will be declared surplus to the nation's needs. Safeguards termination of SNM varies due to the wide range of attractiveness level of the potential material that may be directly discarded as waste. To enhance the efficiency of shipping waste with high TRU fissile content to WIPP, DOE designed an over-pack container, similar to the pipe component, called the criticality control over-pack, which will significantly enhance the efficiency of disposal. Hundreds of shipments of transuranic SNM, suitably packaged to meet WIPP waste acceptance criteria and with safeguards terminated have been successfully emplaced at WIPP (primarily from the Rocky Flats site clean-up) since WIPP opened. DOE expects that thousands more may eventually result from SNM consolidation efforts throughout the weapons complex. (authors)

  20. Next Generation Nuclear Plant Reactor Pressure Vessel Materials Research and Development Plan (PLN-2803)

    SciTech Connect (OSTI)

    J. K. Wright; R. N. Wright

    2010-07-01

    The U.S. Department of Energy (DOE) has selected the High-Temperature Gas-cooled Reactor (HTGR) design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production, with an outlet gas temperature in the range of 750°C, and a design service life of 60 years. The reactor design will be a graphite-moderated, helium-cooled, prismatic, or pebble bed reactor and use low-enriched uranium, Tri-Isotopic (TRISO)-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. Selection of the technology and design configuration for the NGNP must consider both the cost and risk profiles to ensure that the demonstration plant establishes a sound foundation for future commercial deployments. The NGNP challenge is to achieve a significant advancement in nuclear technology while setting the stage for an economically viable deployment of the new technology in the commercial sector soon after 2020. This technology development plan details the additional research and development (R&D) required to design and license the NGNP RPV, assuming that A 508/A 533 is the material of construction. The majority of additional information that is required is related to long-term aging behavior at NGNP vessel temperatures, which are somewhat above those commonly encountered in the existing database from LWR experience. Additional data are also required for the anticipated NGNP environment. An assessment of required R&D for a Grade 91 vessel has been retained from the first revision of the R&D plan in Appendix B in somewhat less detail. Considerably more development is required for this steel compared to A 508/A 533 including additional irradiation testing for expected NGNP operating temperatures, high-temperature mechanical properties, and extensive studies of long-term microstructural stability.

  1. Offsite environmental monitoring report: Radiation monitoring around United States nuclear test areas, calendar year 1993

    SciTech Connect (OSTI)

    Chaloud, D.J; Daigler, D.M.; Davis, M.G.

    1996-06-01

    This report describes the Offsite Radiation Safety Program conducted during 1993 by the Environmental Protection Agency`s (EPA`s) Environmental Monitoring Systems Laboratory - Las Vegas (EMSL-LV). This laboratory operates an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether current radiation levels and associated doses to the general public are in compliance with existing radiation protection standards. The surveillance program additionally has the responsibility to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling milk, water, and air; by deploying thermoluminescent dosimeters (TLDs) and using pressurized ionization chambers (PICs); by biological monitoring of foodstuffs including animal tissues and food crops; and by measurement of radioactive material deposited in humans.

  2. Next Generation Nuclear Plant Reactor Pressure Vessel Materials Research and Development Plan (PLN-2803)

    SciTech Connect (OSTI)

    J. K. Wright; R. N. Wright

    2008-04-01

    The U.S. Department of Energy has selected the High Temperature Gas-cooled Reactor design for the Next Generation Nuclear Plant (NGNP) Project. The NGNP will demonstrate the use of nuclear power for electricity and hydrogen production. It will have an outlet gas temperature in the range of 900°C and a plant design service life of 60 years. The reactor design will be a graphite moderated, helium-cooled, prismatic, or pebble-bed reactor and use low-enriched uranium, Tri-Isotopic-coated fuel. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents. The NGNP Materials Research and Development Program is responsible for performing research and development on likely NGNP materials in support of the NGNP design, licensing, and construction activities. Selection of the technology and design configuration for the NGNP must consider both the cost and risk profiles to ensure that the demonstration plant establishes a sound foundation for future commercial deployments. The NGNP challenge is to achieve a significant advancement in nuclear technology while setting the stage for an economically viable deployment of the new technology in the commercial sector soon after 2020. Studies of potential Reactor Pressure Vessel (RPV) steels have been carried out as part of the pre-conceptual design studies. These design studies generally focus on American Society of Mechanical Engineers (ASME) Code status of the steels, temperature limits, and allowable stresses. Three realistic candidate materials have been identified by this process: conventional light water reactor RPV steels A508/533, 2¼Cr-1Mo in the annealed condition, and modified 9Cr 1Mo ferritic martenistic steel. Based on superior strength and higher temperature limits, the modified 9Cr-1Mo steel has been identified by the majority of design engineers as the preferred choice for the RPV. All of the vendors have concluded, however, that with adequate engineered cooling of the vessel, the A508/533 steels are also acceptable.

  3. Corrective Action Decision Document/Closure Report for Corrective Action Unit 529: Area 25 Contaminated Materials, Nevada Test Site, Nevada, Rev. No.: 1

    SciTech Connect (OSTI)

    Robert F. Boehlecke

    2004-11-01

    This Corrective Action Decision Document (CADD)/Closure Report (CR) has been prepared for Corrective Action Unit (CAU) 529, Area 25 Contaminated Materials, Nevada Test Site (NTS), Nevada, in accordance with the ''Federal Facility Agreement and Consent Order'' (FFACO) that was agreed to by the State of Nevada, U.S. Department of Energy (DOE), and the U.S. Department of Defense (FFACO, 1996). The NTS is approximately 65 miles (mi) northwest of Las Vegas, Nevada (Figure 1-1). Corrective Action Site (CAS) 25-23-17, Contaminated Wash, is the only CAS in CAU 529 and is located in Area 25 of the NTS, in Nye County, Nevada (Figure 1-2). Corrective Action Site 25-23-17, Contaminated Wash, was divided into nine parcels because of the large area impacted by past operations and the complexity of the source areas. The CAS was subdivided into separate parcels based on separate and distinct releases as determined and approved in the Data Quality Objectives (DQO) process and Corrective Action Investigation Plan (CAIP). Table 1-1 summarizes the suspected sources for the nine parcels. Corrective Action Site 25-23-17 is comprised of the following nine parcels: (1) Parcel A, Kiwi Transient Nuclear Test (TNT) 16,000-foot (ft) Arc Area (Kiwi TNT); (2) Parcel B, Phoebus 1A Test 8,000-ft Arc Area (Phoebus); (3) Parcel C, Topopah Wash at Test Cell C (TCC); (4) Parcel D, Buried Contaminated Soil Area (BCSA) l; (5) Parcel E, BCSA 2; (6) Parcel F, Borrow Pit Burial Site (BPBS); (7) Parcel G, Drain/Outfall Discharges; (8) Parcel H, Contaminated Soil Storage Area (CSSA); and (9) Parcel J, Main Stream/Drainage Channels.

  4. Mobile Pit verification system design based on passive special nuclear material verification in weapons storage facilities

    SciTech Connect (OSTI)

    Paul, J. N.; Chin, M. R.; Sjoden, G. E.

    2013-07-01

    A mobile 'drive by' passive radiation detection system to be applied in special nuclear materials (SNM) storage facilities for validation and compliance purposes has been designed through the use of computational modeling and new radiation detection methods. This project was the result of work over a 1 year period to create optimal design specifications to include creation of 3D models using both Monte Carlo and deterministic codes to characterize the gamma and neutron leakage out each surface of SNM-bearing canisters. Results were compared and agreement was demonstrated between both models. Container leakages were then used to determine the expected reaction rates using transport theory in the detectors when placed at varying distances from the can. A 'typical' background signature was incorporated to determine the minimum signatures versus the probability of detection to evaluate moving source protocols with collimation. This established the criteria for verification of source presence and time gating at a given vehicle speed. New methods for the passive detection of SNM were employed and shown to give reliable identification of age and material for highly enriched uranium (HEU) and weapons grade plutonium (WGPu). The finalized 'Mobile Pit Verification System' (MPVS) design demonstrated that a 'drive-by' detection system, collimated and operating at nominally 2 mph, is capable of rapidly verifying each and every weapon pit stored in regularly spaced, shelved storage containers, using completely passive gamma and neutron signatures for HEU and WGPu. This system is ready for real evaluation to demonstrate passive total material accountability in storage facilities. (authors)

  5. ENVIRONMENTAL IlONITORING REPORT FOR THE NEVADA TEST SITE AND OTHER TEST AREAS USED FOR UNDERGROUND NUCLEAR DETONATIONS

    Office of Legacy Management (LM)

    IlONITORING REPORT FOR THE NEVADA TEST SITE AND OTHER TEST AREAS USED FOR UNDERGROUND NUCLEAR DETONATIONS January through December 1975 Nonitoring Operations Division Environmental Monitoring and Support Laboratory U.S. ENVIRONMENTAL PROTECTION AGENCY Las Vegas, Nevada 89114 APRIL 1976 This work performed under a Memorandum of Understanding No. AT(26-1)-539 for the U . S . ENERGY RESEARCH & DEVELOPMENT ADMINISTRATION EMSL-LV-5 39-4 May 1976 ENVIRONMENTAL 14ONITORING REPORT FOR THE NEVADA

  6. Fast-neutron coded-aperture imaging of special nuclear material configurations

    SciTech Connect (OSTI)

    P. A. Hausladen; M. A. Blackston; E. Brubaker; D. L. Chichester; P. Marleau; R. J. Newby

    2012-07-01

    In the past year, a prototype fast-neutron coded-aperture imager has been developed that has sufficient efficiency and resolution to make the counting of warheads for possible future treaty confirmation scenarios via their fission-neutron emissions practical. The imager is constructed from custom-built pixelated liquid scintillator detectors. The liquid scintillator detectors enable neutron-gamma discrimination via pulse shape, and the pixelated construction enables a sufficient number of pixels for imaging in a compact detector with a manageable number of channels of readout electronics. The imager has been used to image neutron sources at ORNL, special nuclear material (SNM) sources at the Idaho National Laboratory (INL) Zero Power Physics Reactor (ZPPR) facility, and neutron source and shielding configurations at Sandia National Laboratories. This paper reports on the design and construction of the imager, characterization measurements with neutron sources at ORNL, and measurements with SNM at the INL ZPPR facility.

  7. Depleted uranium oxides and silicates as spent nuclear fuel waste package fill materials

    SciTech Connect (OSTI)

    Forsberg, C.W.

    1996-09-10

    A new repository waste package (WP) concept for spent nuclear fuel (SNF) is being investigated that uses depleted uranium (DU) to improve performance and reduce the uncertainties of geological disposal of SNF. The WP would be filled with SNF and then filled with depleted uranium (DU) ({approximately}0.2 wt % {sup 235}U) dioxide (UO{sub 2}) or DU silicate-glass beads. Fission products and actinides can not escape the SNF UO{sub 2} crystals until the UO{sub 2} dissolves or is transformed into other chemical species. After WP failure, the DU fill material slows dissolution by three mechanisms: (1) saturation of AT groundwater with DU and suppression of SNF dissolution, (2) maintenance of chemically reducing conditions in the WP that minimize SNF solubility by sacrificial oxidation of DU from the +4 valence state, and (3) evolution of DU to lower-density hydrated uranium silicates. The fill expansion seals the WP from water flow. The DU also isotopically exchanges with SNF uranium as the SNF degrades to reduce long-term nuclear-criticality concerns.

  8. Summary report on transportation of nuclear fuel materials in Japan : transportation infrastructure, threats identified in open literature, and physical protection regulations.

    SciTech Connect (OSTI)

    Cochran, John Russell; Ouchi, Yuichiro (Japan Atomic Energy Agency, Japan); Furaus, James Phillip; Marincel, Michelle K.

    2008-03-01

    This report summarizes the results of three detailed studies of the physical protection systems for the protection of nuclear materials transport in Japan, with an emphasis on the transportation of mixed oxide fuel materials1. The Japanese infrastructure for transporting nuclear fuel materials is addressed in the first section. The second section of this report presents a summary of baseline data from the open literature on the threats of sabotage and theft during the transport of nuclear fuel materials in Japan. The third section summarizes a review of current International Atomic Energy Agency, Japanese and United States guidelines and regulations concerning the physical protection for the transportation of nuclear fuel materials.

  9. Offsite environmental monitoring report. Radiation monitoring around United States nuclear test areas, calendar year 1981

    SciTech Connect (OSTI)

    Black, S.C.; Grossman, R.F.; Mullen, A.A.; Potter, G.D.; Smith, D.D.; Hopper, J.L.

    1982-08-01

    This report, prepared in accordance with the guidelines in DOE/E-0023 (DOE 1981), covers the program activities conducted around Nevada Test Site (NTS) for calendar year 1981. It contains descriptions of pertinent features of the NTS and its environs, summaries of the dosimetry and sampling methods, analytical procedures, and the analytical results from environmental measurements. Where applicable, dosimetry and sampling data are compared to appropriate guides for external and internal exposures of humans to ionizing radiation. The monitoring networks detected no radioactivity in the various media which could be attributed to US nuclear testing. Small amounts of fission products were detected in air samples as a result of the People's Republic of China nuclear test and atmospheric krypton-85 increased, following the trend beginning in 1960, due to increased use of nuclear technology. Strontium-90 in milk and cesium-137 in meat samples continued the slow decline as observed for the last several years.

  10. Modeling most likely pathways for smuggling radioactive and special nuclear materials on a worldwide multi-modal transportation network

    SciTech Connect (OSTI)

    Saeger, Kevin J [Los Alamos National Laboratory; Cuellar, Leticia [Los Alamos National Laboratory

    2010-10-28

    Nuclear weapons proliferation is an existing and growing worldwide problem. To help with devising strategies and supporting decisions to interdict the transport of nuclear material, we developed the Pathway Analysis, Threat Response and Interdiction Options Tool (PATRIOT) that provides an analytical approach for evaluating the probability that an adversary smuggling radioactive or special nuclear material will be detected during transit. We incorporate a global, multi-modal transportation network, explicit representation of designed and serendipitous detection opportunities, and multiple threat devices, material types, and shielding levels. This paper presents the general structure of PATRIOT, all focuses on the theoretical framework used to model the reliabilities of all network components that are used to predict the most likely pathways to the target.

  11. Development of improved thermoelectric materials for space nuclear power systems. Sixth technical progress report, March 1985

    SciTech Connect (OSTI)

    Not Available

    1985-01-01

    The program consists of two main tasks encompassing (1) the development of an improved SiGe alloy and (2) the development of an as yet unspecified advanced material intended to have superior performance characteristics when compared to SiGe alloys. Significant progress was made toward the goal of producing a SiGe based material with an improved figure-of-merit during this reporting period. In these studies, a quantitative evaluation of the characteristics which produce the low thermal conductivities observed in SiGe alloys is being developed. Specific areas of emphasis include the effects of grain size, charge carrier and GaP concentrations. An alternate method for alloying with GaP was evaluated in which the GaP was added to SiGe during the melting operation.

  12. Preliminary materials selection issues for the next generation nuclear plant reactor pressure vessel.

    SciTech Connect (OSTI)

    Natesan, K.; Majumdar, S.; Shankar, P. S.; Shah, V. N.; Nuclear Engineering Division

    2007-03-21

    In the coming decades, the United States and the entire world will need energy supplies to meet the growing demands due to population increase and increase in consumption due to global industrialization. One of the reactor system concepts, the Very High Temperature Reactor (VHTR), with helium as the coolant, has been identified as uniquely suited for producing hydrogen without consumption of fossil fuels or the emission of greenhouse gases [Generation IV 2002]. The U.S. Department of Energy (DOE) has selected this system for the Next Generation Nuclear Plant (NGNP) Project, to demonstrate emissions-free nuclear-assisted electricity and hydrogen production within the next 15 years. The NGNP reference concepts are helium-cooled, graphite-moderated, thermal neutron spectrum reactors with a design goal outlet helium temperature of {approx}1000 C [MacDonald et al. 2004]. The reactor core could be either a prismatic graphite block type core or a pebble bed core. The use of molten salt coolant, especially for the transfer of heat to hydrogen production, is also being considered. The NGNP is expected to produce both electricity and hydrogen. The process heat for hydrogen production will be transferred to the hydrogen plant through an intermediate heat exchanger (IHX). The basic technology for the NGNP has been established in the former high temperature gas reactor (HTGR) and demonstration plants (DRAGON, Peach Bottom, AVR, Fort St. Vrain, and THTR). In addition, the technologies for the NGNP are being advanced in the Gas Turbine-Modular Helium Reactor (GT-MHR) project, and the South African state utility ESKOM-sponsored project to develop the Pebble Bed Modular Reactor (PBMR). Furthermore, the Japanese HTTR and Chinese HTR-10 test reactors are demonstrating the feasibility of some of the planned components and materials. The proposed high operating temperatures in the VHTR place significant constraints on the choice of material selected for the reactor pressure vessel for both the PBMR and prismatic design. The main focus of this report is the RPV for both design concepts with emphasis on material selection.

  13. DOE issues Finding of No Significant Impact for the Environmental Assessment on Resumption of Transient Testing of Nuclear Fuels and Materials at Idaho National Laboratory

    Broader source: Energy.gov [DOE]

    DOE issues Finding of No Significant Impact for the Environmental Assessment on Resumption of Transient Testing of Nuclear Fuels and Materials at Idaho National Laboratory

  14. International training course on implementation of state systems of accounting for and control of nuclear materials: proceedings

    SciTech Connect (OSTI)

    Not Available

    1984-06-01

    This report incorporates all lectures and presentations at the International Training Course on Implementation of State Systems of Accounting for and Control of Nuclear Materials held October 17 through November 4, 1983, at Santa Fe and Los Alamos, New Mexico and Richland, Washington, USA. Authorized by the US Nuclear Non-Proliferation Act and sponsored by the US Department of Energy in cooperation with the International Atomic Energy Agency, the course was developed to provide practical training in the design, implementation, and operation of a State system of nuclear materials accountability and control that satisfies both national and international safeguards requirements. Major emphasis for the 1983 course was placed on safeguards methods used at bulk-handling facilities, particularly low-enriched uranium conversion and fuel fabrication plants. The course was conducted by the University of California's Los Alamos National Laboratory and Exxon Nuclear Company, Inc. Tours and demonstrations were arranged at the Los Alamos National Laboratory, Los Alamos, New Mexico, and the Exxon Nuclear fuel fabrication plant, the Battelle Pacific Northwest Laboratory, Westinghouse Fast Flux Test Facility Visitor Center, and Washington Public Power System nuclear reactor facilities in Richland, Washington. Individual presentations were indexed for inclusion in the Energy Data Base.

  15. Fuel-Cycle and Nuclear Material Disposition Issues Associated with High-Temperature Gas Reactors

    SciTech Connect (OSTI)

    Shropshire, D.E.; Herring, J.S.

    2004-10-03

    The objective of this paper is to facilitate a better understanding of the fuel-cycle and nuclear material disposition issues associated with high-temperature gas reactors (HTGRs). This paper reviews the nuclear fuel cycles supporting early and present day gas reactors, and identifies challenges for the advanced fuel cycles and waste management systems supporting the next generation of HTGRs, including the Very High Temperature Reactor, which is under development in the Generation IV Program. The earliest gas-cooled reactors were the carbon dioxide (CO2)-cooled reactors. Historical experience is available from over 1,000 reactor-years of operation from 52 electricity-generating, CO2-cooled reactor plants that were placed in operation worldwide. Following the CO2 reactor development, seven HTGR plants were built and operated. The HTGR came about from the combination of helium coolant and graphite moderator. Helium was used instead of air or CO2 as the coolant. The helium gas has a significant technical base due to the experience gained in the United States from the 40-MWe Peach Bottom and 330-MWe Fort St. Vrain reactors designed by General Atomics. Germany also built and operated the 15-MWe Arbeitsgemeinschaft Versuchsreaktor (AVR) and the 300-MWe Thorium High-Temperature Reactor (THTR) power plants. The AVR, THTR, Peach Bottom and Fort St. Vrain all used fuel containing thorium in various forms (i.e., carbides, oxides, thorium particles) and mixtures with highly enriched uranium. The operational experience gained from these early gas reactors can be applied to the next generation of nuclear power systems. HTGR systems are being developed in South Africa, China, Japan, the United States, and Russia. Elements of the HTGR system evaluated included fuel demands on uranium ore mining and milling, conversion, enrichment services, and fuel fabrication; fuel management in-core; spent fuel characteristics affecting fuel recycling and refabrication, fuel handling, interim storage, packaging, transportation, waste forms, waste treatment, decontamination and decommissioning issues; and low-level waste (LLW) and high-level waste (HLW) disposal.

  16. Filter Measurement System for Nuclear Material Storage Canisters. End of Year Report FY 2013

    SciTech Connect (OSTI)

    Moore, Murray E. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Reeves, Kirk P. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-02-03

    A test system has been developed at Los Alamos National Laboratory to measure the aerosol collection efficiency of filters in the lids of storage canisters for special nuclear materials. Two FTS (filter test system) devices have been constructed; one will be used in the LANL TA-55 facility with lids from canisters that have stored nuclear material. The other FTS device will be used in TA-3 at the Radiation Protection Divisions Aerosol Engineering Facility. The TA-3 system will have an expanded analytical capability, compared to the TA-55 system that will be used for operational performance testing. The LANL FTS is intended to be automatic in operation, with independent instrument checks for each system component. The FTS has been described in a complete P&ID (piping and instrumentation diagram) sketch, included in this report. The TA-3 FTS system is currently in a proof-of-concept status, and TA-55 FTS is a production-quality prototype. The LANL specification for (Hagan and SAVY) storage canisters requires the filter shall capture greater than 99.97% of 0.45-micron mean diameter dioctyl phthalate (DOP) aerosol at the rated flow with a DOP concentration of 6515 micrograms per liter. The percent penetration (PEN%) and pressure drop (DP) of fifteen (15) Hagan canister lids were measured by NFT Inc. (Golden, CO) over a period of time, starting in the year 2002. The Los Alamos FTS measured these quantities on June 21, 2013 and on Oct. 30, 2013. The LANL(6-21-2013) results did not statistically match the NFT Inc. data, and the LANL FTS system was re-evaluated, and the aerosol generator was replaced and the air flow measurement method was corrected. The subsequent LANL(10-30-2013) tests indicate that the PEN% results are statistically identical to the NFT Inc. results. The LANL(10-30-2013) pressure drop measurements are closer to the NFT Inc. data, but future work will be investigated. An operating procedure for the FTS (filter test system) was written, and future project milestones are on track for completion

  17. EA-1954: Resumption of Transient Testing of Nuclear Fuels and Materials at the Idaho National Laboratory, Idaho

    Broader source: Energy.gov [DOE]

    This Environmental Assessment (EA) evaluates U.S. Department of Energy (DOE) activities associated with its proposal to resume testing of nuclear fuels and materials under transient high-power test conditions at the Transient Reactor Test (TREAT) Facility at the Idaho National Laboratory. The State of Idaho and Shoshone-Bannock Tribes are cooperating agencies.

  18. Packaging and Transportation for Offsite Shipment of Materials...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    1.1C Second Draft, Packaging and Transportation for Offsite Shipment of Materials of National Security Interests by Matthew Weber Functional areas: Defense Nuclear Facility Safety...

  19. Packaging and Transportation for Offsite Shipment of Materials...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    of Materials of National Security Interests by Matthew Weber Functional areas: Defense Nuclear Facility Safety and Health Requirement, Packaging and Transportation, Security,...

  20. Performance Assessment and Composit Analysis Material Disposal Area G Revision 4

    Broader source: Energy.gov [DOE]

    Los Alamos National Laboratory (LANL or the Laboratory) generates radioactive waste as a result of various activities. Most is low-level radioactive waste that is disposed of at Technical Area (TA) 54, Area G. U.S. Department of Energy (DOE) Order 435.1 requires that DOE field sites prepare and maintain site-specific radiological performance assessments and composite analyses for lowlevel radioactive waste disposal facilities that accept waste after September 26, 1988. This report presents the radiological performance assessment and composite analysis for TA 54, Area G. The performance assessment and composite analysis model the long-term performance of the Area G disposal facility so that the risk posed by the disposed waste to human health and safety and the environment can be determined. Rates of radionuclide release from the waste and the transport of these releases to locations accessible to humans are evaluated and used to project radiation doses that may be received by exposed persons. The release rates of radon gas from the disposal facility are also estimated. The dose and radon flux projections are compared to the performance objectives provided in DOE M 435.1 to evaluate the ability of the disposal facility to safely isolate the waste.

  1. nuclear

    National Nuclear Security Administration (NNSA)

    2%2A en U.S-, Japan Exchange Best Practices on Nuclear Emergency Response http:nnsa.energy.govmediaroompressreleasesu.s-japan-exchange-best-practices-nuclear-emergency-respon...

  2. E-Area Vault Concrete Material Property And Vault Durability/Degradation Projection Recommendations

    SciTech Connect (OSTI)

    Phifer, M. A.

    2014-03-11

    Subsequent to the 2008 E-Area Low-Level Waste Facility (ELLWF) Performance Assessment (PA) (WSRC 2008), two additional E-Area vault concrete property testing programs have been conducted (Dixon and Phifer 2010 and SIMCO 2011a) and two additional E-Area vault concrete durability modeling projections have been made (Langton 2009 and SIMCO 2012). All the information/data from these reports has been evaluated and consolidated herein by the Savannah River National Laboratory (SRNL) at the request of Solid Waste Management (SWM) to produce E-Area vault concrete hydraulic and physical property data and vault durability/degradation projection recommendations that are adequately justified for use within associated Special Analyses (SAs) and future PA updates. The Low Activity Waste (LAW) and Intermediate Level (IL) Vaults structural degradation predictions produced by Carey 2006 and Peregoy 2006, respectively, which were used as the basis for the 2008 ELLWF PA, remain valid based upon the results of the E-Area vault concrete durability simulations reported by Langton 2009 and those reported by SIMCO 2012. Therefore revised structural degradation predictions are not required so long as the mean thickness of the closure cap overlying the vaults is no greater than that assumed within Carey 2006 and Peregoy 2006. For the LAW Vault structural degradation prediction (Carey 2006), the mean thickness of the overlying closure cap was taken as nine feet. For the IL Vault structural degradation prediction (Peregoy 2006), the mean thickness of the overlying closure cap was taken as eight feet. The mean closure cap thicknesses as described here for both E-Area Vaults will be included as a key input and assumption (I&A) in the next revision to the closure plan for the ELLWF (Phifer et al. 2009). In addition, it has been identified as new input to the PA model to be assessed in the ongoing update to the new PA Information UDQE (Flach 2013). Once the UDQE is approved, the SWM Key I&A database will be updated with this new information.

  3. Cyclododecane as support material for clean and facile transfer of large-area few-layer graphene

    SciTech Connect (OSTI)

    Capasso, A.; Leoni, E.; Dikonimos, T.; Buonocore, F.; Lisi, N. [ENEA, Materials Technology Unit, Surface Technology Laboratory, Casaccia Research Centre, Via Anguillarese 301, 00060 Rome (Italy); De Francesco, M. [ENEA, Technical Unit for Renewable Energies Sources, Casaccia Research Center, Via Anguillarese 301, 00060 Rome (Italy); Lancellotti, L.; Bobeico, E. [ENEA, Portici Research Centre, P.le E. Fermi 1, 80055 Portici (Italy); Sarto, M. S.; Tamburrano, A.; De Bellis, G. [Research Center on Nanotechnology Applied to Engineering of Sapienza (CNIS), SSNLab, Sapienza University of Rome, P.le Aldo Moro 5, 00185 Rome (Italy)

    2014-09-15

    The transfer of chemical vapor deposited graphene is a crucial process, which can affect the quality of the transferred films and compromise their application in devices. Finding a robust and intrinsically clean material capable of easing the transfer of graphene without interfering with its properties remains a challenge. We here propose the use of an organic compound, cyclododecane, as a transfer material. This material can be easily spin coated on graphene and assist the transfer, leaving no residues and requiring no further removal processes. The effectiveness of this transfer method for few-layer graphene on a large area was evaluated and confirmed by microscopy, Raman spectroscopy, x-ray photoemission spectroscopy, and four-point probe measurements. Schottky-barrier solar cells with few-layer graphene were fabricated on silicon wafers by using the cyclododecane transfer method and outperformed reference cells made by standard methods.

  4. International training course on implementation of state systems of accounting for and control of nuclear materials: proceedings

    SciTech Connect (OSTI)

    Not Available

    1986-06-01

    This report incorporates all lectures and presentations at the International Training Course on Implementation of State Systems of Accounting for and Control of Nuclear Materials held June 3 through June 21, 1985, at Santa Fe and Los Alamos, New Mexico, and San Clemente, California. Authorized by the US Nuclear Non-Proliferation Act and sponsored by the US Department of Energy in cooperation with the International Atomic Energy Agency, the Course was developed to provide practical training in the design, implementation, and operation of a state system of nuclear materials accountability and control that satisfies both national and international safeguards requirements. Major emphasis for the 1985 course was placed on safeguards methods used at item-control facilities, particularly nuclear power generating stations and test reactors. An introduction to safeguards methods used at bulk handling facilities, particularly low-enriched uranium conversion and fuel fabrication plants, was also included. The course was conducted by the University of California's Los Alamos National Laboratory and the Southern California Edison Company. Tours and demonstrations were arranged at the Los Alamos National Laboratory, Los Alamos, New Mexico, and the San Onofre Nuclear Generating Station, San Clemente, California.

  5. The Development of a Parameterized Scatter Removal Algorithm for Nuclear Materials Identification System Imaging

    SciTech Connect (OSTI)

    Grogan, Brandon R

    2010-03-01

    This dissertation presents a novel method for removing scattering effects from Nuclear Materials Identification System (NMIS) imaging. The NMIS uses fast neutron radiography to generate images of the internal structure of objects non-intrusively. If the correct attenuation through the object is measured, the positions and macroscopic cross-sections of features inside the object can be determined. The cross sections can then be used to identify the materials and a 3D map of the interior of the object can be reconstructed. Unfortunately, the measured attenuation values are always too low because scattered neutrons contribute to the unattenuated neutron signal. Previous efforts to remove the scatter from NMIS imaging have focused on minimizing the fraction of scattered neutrons which are misidentified as directly transmitted by electronically collimating and time tagging the source neutrons. The parameterized scatter removal algorithm (PSRA) approaches the problem from an entirely new direction by using Monte Carlo simulations to estimate the point scatter functions (PScFs) produced by neutrons scattering in the object. PScFs have been used to remove scattering successfully in other applications, but only with simple 2D detector models. This work represents the first time PScFs have ever been applied to an imaging detector geometry as complicated as the NMIS. By fitting the PScFs using a Gaussian function, they can be parameterized and the proper scatter for a given problem can be removed without the need for rerunning the simulations each time. In order to model the PScFs, an entirely new method for simulating NMIS measurements was developed for this work. The development of the new models and the codes required to simulate them are presented in detail. The PSRA was used on several simulated and experimental measurements and chi-squared goodness of fit tests were used to compare the corrected values to the ideal values that would be expected with no scattering. Using the PSRA resulted in an improvement of the chi-squared test by a factor of 60 or more when applied to simple homogeneous objects.

  6. Evaluation of Aluminum-Boron Carbide Neutron Absorbing Materials for Interim Storage of Used Nuclear Fuel

    SciTech Connect (OSTI)

    Wang, Lumin; Wierschke, Jonathan Brett

    2015-04-08

    The objective of this work was to understand the corrosion behavior of Boral® and Bortec® neutron absorbers over long-term deployment in a used nuclear fuel dry cask storage environment. Corrosion effects were accelerated by flowing humidified argon through an autoclave at temperatures up to 570°C. Test results show little corrosion of the aluminum matrix but that boron is leaching out of the samples. Initial tests performed at 400 and 570°C were hampered by reduced flow caused by the rapid build-up of solid deposits in the outlet lines. Analysis of the deposits by XRD shows that the deposits are comprised of boron trioxide and sassolite (H3BO3). The collection of boron- containing compounds in the outlet lines indicated that boron was being released from the samples. Observation of the exposed samples using SEM and optical microscopy show the growth of new phases in the samples. These phases were most prominent in Bortec® samples exposed at 570°C. Samples of Boral® exposed at 570°C showed minimal new phase formation but showed nearly the complete loss of boron carbide particles. Boron carbide loss was also significant in Boral samples at 400°C. However, at 400°C phases similar to those found in Bortec® were observed. The rapid loss of the boron carbide particles in the Boral® is suspected to inhibit the formation of the new secondary phases. However, Material samples in an actual dry cask environment would be exposed to temperatures closer to 300°C and less water than the lowest test. The results from this study conclude that at the temperature and humidity levels present in a dry cask environment, corrosion and boron leaching will have no effect on the performance of Boral® and Bortec® to maintain criticality control.

  7. Nuclear Forensics

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Nuclear Forensics AMS is a Powerful Tool for Nuclear Forensics Nuclear forensics, which can be applied to both interdicted materials and debris from a nuclear explosion, is the application of laboratory analysis and interpretation to provide technical conclusions (provenance, design, etc.) about a nuclear device or interdicted nuclear material. Nuclear forensic analysts can build confidence in their conclusions by employing multiple signatures that collectively minimize the subset of possible

  8. Gamma/neutron time-correlation for special nuclear material detection Active stimulation of highly enriched uranium

    SciTech Connect (OSTI)

    Paff, Marc G.; Monterial, Mateusz; Marleau, Peter; Kiff, Scott; Nowack, Aaron; Clarke, Shaun D.; Pozzi, Sara A.

    2014-06-21

    A series of simulations and experiments were undertaken to explore and evaluate the potential for a novel new technique for fissile material detection and characterization, the timecorrelated pulse-height (TCPH) method, to be used concurrent with active stimulation of potential nuclear materials. In previous work TCPH has been established as a highly sensitive method for the detection and characterization of configurations of fissile material containing Plutonium in passive measurements. By actively stimulating fission with the introduction of an external radiation source, we have shown that TCPH is also an effective method of detecting and characterizing configurations of fissile material containing Highly Enriched Uranium (HEU). The TCPH method is shown to be robust in the presence of the proper choice of external radiation source. An evaluation of potential interrogation sources is presented.

  9. Gamma/neutron time-correlation for special nuclear material detection – Active stimulation of highly enriched uranium

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Paff, Marc G.; Monterial, Mateusz; Marleau, Peter; Kiff, Scott; Nowack, Aaron; Clarke, Shaun D.; Pozzi, Sara A.

    2014-06-21

    A series of simulations and experiments were undertaken to explore and evaluate the potential for a novel new technique for fissile material detection and characterization, the timecorrelated pulse-height (TCPH) method, to be used concurrent with active stimulation of potential nuclear materials. In previous work TCPH has been established as a highly sensitive method for the detection and characterization of configurations of fissile material containing Plutonium in passive measurements. By actively stimulating fission with the introduction of an external radiation source, we have shown that TCPH is also an effective method of detecting and characterizing configurations of fissile material containing Highlymore » Enriched Uranium (HEU). The TCPH method is shown to be robust in the presence of the proper choice of external radiation source. An evaluation of potential interrogation sources is presented.« less

  10. 20th International Training Course (ITC-20) on the physical protection of nuclear facilities and materials evaluation report.

    SciTech Connect (OSTI)

    Ramirez, Amanda Ann

    2008-09-01

    The goal of this evaluation report is to provide the information necessary to improve the effectiveness of the ITC provided to the International Atomic Energy Agency Member States. This report examines ITC-20 training content, delivery methods, scheduling, and logistics. Ultimately, this report evaluates whether the course provides the knowledge and skills necessary to meet the participants needs in the protection of nuclear materials and facilities.

  11. Department of Energy Nuclear Material Protection, Control, and Accounting Program at the Mangyshlak Atomic Energy Complex, Aktau, Republic of Kazakhstan

    SciTech Connect (OSTI)

    Case, R.; Berry, R.B.; Eras, A.

    1998-08-01

    As part of the Cooperative Threat Reduction Nuclear Material Protection, Control, and Accounting (MPC and A) Program, the US Department of Energy and Mangyshlak Atomic Energy Complex (MAEC), Aktau, Republic of Kazakstan have cooperated to enhance existing MAEC MPC and A features at the BN-350 liquid-metal fast-breeder reactor. This paper describes the methodology of the enhancement activities and provides representative examples of the MPC and A augmentation implemented at the MAEC.

  12. Offsite environmental monitoring report: Radiation monitoring around United States nuclear test areas, calendar year 1997

    SciTech Connect (OSTI)

    Davis, M.G.; Flotard, R.D.; Fontana, C.A.; Hennessey, P.A.; Maunu, H.K.; Mouck, T.L.; Mullen, A.A.; Sells, M.D.

    1999-01-01

    This report describes the Offsite Radiological Environmental Monitoring Program (OREMP) conducted during 1997 by the US Environmental Protection Agency`s (EPAs), Radiation and Indoor Environments National Laboratory, Las Vegas, Nevada. This laboratory operated an environmental radiation monitoring program in the region surrounding the Nevada Test Site (NTS) and at former test sites in Alaska, Colorado, Mississippi, Nevada, and New Mexico. The surveillance program is designed to measure levels and trends of radioactivity, if present, in the environment surrounding testing areas to ascertain whether current radiation levels and associated doses to the general public are in compliance with existing radiation protection standards. The surveillance program additionally has the responsibility to take action to protect the health and well being of the public in the event of any accidental release of radioactive contaminants. Offsite levels of radiation and radioactivity are assessed by sampling and analyzing milk, water, and air; by deploying and reading thermoluminescent dosimeters (TLDs); and using pressurized ionization chambers (PICs) to measure ambient gamma exposure rates with a sensitivity capable of detecting low level exposures not detected by other monitoring methods.

  13. Materials

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Materials Materials Access to Hopper Phase II (Cray XE6) If you are a current NERSC user, you are enabled to use Hopper Phase II. Use your SSH client to connect to Hopper II:...

  14. Supporting Technology for Chain of Custody of Nuclear Weapons and Materials throughout the Dismantlement and Disposition Processes

    SciTech Connect (OSTI)

    Bunch, Kyle J.; Jones, Anthony M.; Ramuhalli, Pradeep; Benz, Jacob M.; Denlinger, Laura Schmidt

    2014-05-04

    The ratification and ongoing implementation of the New START Treaty have been widely regarded as noteworthy global security achievements for both the Obama Administration and the Putin (formerly Medvedev) regime. But deeper cuts that move beyond the United States and Russia to engage the P-5 and other nuclear weapons possessor states are envisioned under future arms control regimes, and are indeed required for the P-5 in accordance with their Article VI disarmament obligations in the Nuclear Non-Proliferation Treaty. Future verification needs will include monitoring the cessation of production of new fissile material for weapons, monitoring storage of warhead components and fissile materials and verifying dismantlement of warheads, pits, secondary stages, and other materials. A fundamental challenge to implementing a nuclear disarmament regime is the ability to thwart unauthorized material diversion throughout the dismantlement and disposition process through strong chain of custody implementation. Verifying the declared presence, or absence, of nuclear materials and weapons components throughout the dismantlement and disposition lifecycle is a critical aspect of the disarmament process. From both the diplomatic and technical perspectives, verification under these future arms control regimes will require new solutions. Since any acceptable verification technology must protect sensitive design information and attributes to prevent the release of classified or other proliferation-sensitive information, non-nuclear non-sensitive modalities may provide significant new verification tools which do not require the use of additional information barriers. Alternative verification technologies based upon electromagnetic and acoustics could potentially play an important role in fulfilling the challenging requirements of future verification regimes. For example, researchers at the Pacific Northwest National Laboratory (PNNL) have demonstrated that low frequency electromagnetic signatures of sealed metallic containers can be used to rapidly confirm the presence of specific components on a yes/no basis without revealing classified information. PNNL researchers have also used ultrasonic measurements to obtain images of material microstructures which may be used as templates or unique identifiers of treaty-limited items. Such alternative technologies are suitable for application in various stages of weapons dismantlement and often include the advantage of an inherent information barrier due to the inability to extract classified weapon design information from the collected data. As a result, these types of technologies complement radiation-based verification methods for arms control. This article presents an overview of several alternative verification technologies that are suitable for supporting a future, broader and more intrusive arms control regime that spans the nuclear weapons disarmament lifecycle. The general capabilities and limitations of each verification modality are discussed and example technologies are presented. Potential applications are defined in the context of the nuclear material and weapons lifecycle. Example applications range from authentication (e.g., tracking and signatures within the chain of custody from downloading through weapons storage, unclassified templates and unique identification) to verification of absence and final material disposition.

  15. Summary. “Materials Challenges in Nuclear Energy,” S.J. Zinkle, 2013

    SciTech Connect (OSTI)

    Pestovich, Kimberly Shay

    2015-11-05

    Nuclear energy continues to grow in abundance and importance. It offers a future electric grid based entirely off of green energy, and it has numerous applications. Nuclear power has capabilities to desalinate water, deliver process heat or steam, affordably crack hydrogen from water, and extract unconventional fossil fuel sources. Current light water reactors demonstrate high reliability under normal operating conditions. Researchers have shown significant interest and investigating how to extend reactor lifespans and into other possible reactor designs. Further understanding of mechanisms responsible for corrosion and stress corrosion cracking, radiation hardening and degradation, and nuclear fuels innovations can lead to safer, more reliable, and cost-effective water-cooled nuclear reactors for electricity production.

  16. Analytical methods for fissionable material determinations in the nuclear fuel cycle. Progress report, October 1, 1978-September 30, 1979

    SciTech Connect (OSTI)

    Waterbury, G.R.

    1980-03-01

    Work continues on the development of dissolution techniques for difficult-to-dissolve nuclear materials, the development of methods and automated instruments for plutonium, uranium, and thorium determinations, and the preparation of plutonium materials for the Safeguards Analytical Laboratory Evaluation (SALE) program and distribution by the National Bureau of Standards (NBS) as standard reference materials (SRMs). We are measuring the loner plutonium isotope half-lives, evaluating the isotope correlation techniques and the chemistry involved in the mass-spectrometric ion-bead techniques, and analyzing the SALE uranium materials. Completed subtasks include evaluations of various Teflon materials to recommend those acceptable for the dissolution apparatus developed at LASL, investigations of laser-enhanced dissolution of refractory materials, determinations of diverse ion effects on the microgram-sensitive method for determining uranium, fabrication of the first automated controlled-potential coulometric analyzer for determining plutonium, preparation of a /sup 244/Pu material for distribution by NBS as a SRM, and determination of the half-life of /sup 239/Pu. Work has been started on a spectrophotometric method for determining microgram quantities of plutonium, a microcomplexometric titration method for determining uranium, the use of new reagents for separations of plutonium, the preparation and packaging of a new lot of high-purity plutonium metal for distribution by NBS as a plutonium chemical SRM, and determination of half-lives of other plutonium isotopes.

  17. LANL Virtual Center for Chemical Hydrogen Storage: Chemical Hydrogen Storage Using Ultra-high Surface Area Main Group Materials

    SciTech Connect (OSTI)

    Susan M. Kauzlarich; Phillip P. Power; Doinita Neiner; Alex Pickering; Eric Rivard; Bobby Ellis, T. M.; Atkins, A. Merrill; R. Wolf; Julia Wang

    2010-09-05

    The focus of the project was to design and synthesize light element compounds and nanomaterials that will reversibly store molecular hydrogen for hydrogen storage materials. The primary targets investigated during the last year were amine and hydrogen terminated silicon (Si) nanoparticles, Si alloyed with lighter elements (carbon (C) and boron (B)) and boron nanoparticles. The large surface area of nanoparticles should facilitate a favorable weight to volume ratio, while the low molecular weight elements such as B, nitrogen (N), and Si exist in a variety of inexpensive and readily available precursors. Furthermore, small NPs of Si are nontoxic and non-corrosive. Insights gained from these studies will be applied toward the design and synthesis of hydrogen storage materials that meet the DOE 2010 hydrogen storage targets: cost, hydrogen capacity and reversibility. Two primary routes were explored for the production of nanoparticles smaller than 10 nm in diameter. The first was the reduction of the elemental halides to achieve nanomaterials with chloride surface termination that could subsequently be replaced with amine or hydrogen. The second was the reaction of alkali metal Si or Si alloys with ammonium halides to produce hydrogen capped nanomaterials. These materials were characterized via X-ray powder diffraction, TEM, FTIR, TG/DSC, and NMR spectroscopy.

  18. Precursor Derived Nanostructured Si-C-X Materials for Nuclear Applications. Final Report, October 2010 - September 2014

    SciTech Connect (OSTI)

    Bordia, Rajendra; Tomar, Vikas; Henager, Chuck

    2015-04-08

    Polymer derived ceramic route is an attractive approach to make structural materials with unique nanostructures that have very desirable high temperature properties. Processing techniques to make a variety of needed shapes and forms (e.g. coatings, matrices for fiber reinforced composites, porous ceramics) have been developed. With appropriate high temperature processing, the precursors can be converted to nano-crystalline materials. In this collaborative project, we investigated the processing, stability and properties of nanostructured Si-C materials, derived from polymeric precursors, and their performance under conditions appropriate for nuclear energy applications. All the milestones of the project were accomplished. Some of the results are being currently analyzed and additional papers being prepared in which support from NEUP will be acknowledged. So far, eight peer-reviewed papers have been published and one invention disclosure made. In this report, we summarize the major findings of this project.

  19. Final LDRD report : nanoscale mechanisms in advanced aging of materials during storage of spent %22high burnup%22 nuclear fuel.

    SciTech Connect (OSTI)

    Clark, Blythe G.; Rajasekhara, Shreyas; Enos, David George; Dingreville, Remi Philippe Michel; Doyle, Barney Lee; Hattar, Khalid Mikhiel; Weiner, Ruth F.

    2013-09-01

    We present the results of a three-year LDRD project focused on understanding microstructural evolution and related property changes in Zr-based nuclear cladding materials towards the development of high fidelity predictive simulations for long term dry storage. Experiments and modeling efforts have focused on the effects of hydride formation and accumulation of irradiation defects. Key results include: determination of the influence of composition and defect structures on hydride formation; measurement of the electrochemical property differences between hydride and parent material for understanding and predicting corrosion resistance; in situ environmental transmission electron microscope observation of hydride formation; development of a predictive simulation for mechanical property changes as a function of irradiation dose; novel test method development for microtensile testing of ionirradiated material to simulate the effect of neutron irradiation on mechanical properties; and successful demonstration of an Idaho National Labs-based sample preparation and shipping method for subsequent Sandia-based analysis of post-reactor cladding.

  20. An overview of research activities on materials for nuclear applications at the INL Safety, Tritium and Applied Research facility

    SciTech Connect (OSTI)

    P. Calderoni; P. Sharpe; M. Shimada

    2009-09-01

    The Safety, Tritium and Applied Research facility at the Idaho National Laboratory is a US Department of Energy National User Facility engaged in various aspects of materials research for nuclear applications related to fusion and advanced fission systems. Research activities are mainly focused on the interaction of tritium with materials, in particular plasma facing components, liquid breeders, high temperature coolants, fuel cladding, cooling and blanket structures and heat exchangers. Other activities include validation and verification experiments in support of the Fusion Safety Program, such as beryllium dust reactivity and dust transport in vacuum vessels, and support of Advanced Test Reactor irradiation experiments. This paper presents an overview of the programs engaged in the activities, which include the US-Japan TITAN collaboration, the US ITER program, the Next Generation Power Plant program and the tritium production program, and a presentation of ongoing experiments as well as a summary of recent results with emphasis on fusion relevant materials.

  1. Addendum to the Corrective Action Decision Document/Closure Report for Corrective Action Unit 529: Area 25 Contaminated Materials, Nevada Test Site, Nevada, Revision 1

    SciTech Connect (OSTI)

    Krauss, Mark J

    2013-10-01

    This document constitutes an addendum to the Corrective Action Decision Document/Closure Report for Corrective Action Unit 529: Area 25 Contaminated Materials, Nevada Test Site, Nevada as described in the document Recommendations and Justifications To Remove Use Restrictions Established under the U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office Federal Facility Agreement and Consent Order dated September 2013. The Use Restriction (UR) Removal document was approved by the Nevada Division of Environmental Protection on October 16, 2013. The approval of the UR Removal document constituted approval of each of the recommended UR removals. In conformance with the UR Removal document, this addendum consists of: This page that refers the reader to the UR Removal document for additional information The cover, title, and signature pages of the UR Removal document The NDEP approval letter The corresponding section of the UR Removal document This addendum provides the documentation justifying the cancellation of the UR for CAS 25-23-17, Contaminated Wash (Parcel H). This UR was established as part of FFACO corrective actions and was based on the presence of total petroleum hydrocarbon diesel-range organics contamination at concentrations greater than the NDEP action level at the time of the initial investigation.

  2. Emergency preparedness source term development for the Office of Nuclear Material Safety and Safeguards-Licensed Facilities

    SciTech Connect (OSTI)

    Sutter, S.L.; Mishima, J.; Ballinger, M.Y.; Lindsey, C.G.

    1984-08-01

    In order to establish requirements for emergency preparedness plans at facilities licensed by the Office of Nuclear Materials Safety and Safeguards, the Nuclear Regulatory Commission (NRC) needs to develop source terms (the amount of material made airborne) in accidents. These source terms are used to estimate the potential public doses from the events, which, in turn, will be used to judge whether emergency preparedness plans are needed for a particular type of facility. Pacific Northwest Laboratory is providing the NRC with source terms by developing several accident scenarios for eleven types of fuel cycle and by-product operations. Several scenarios are developed for each operation, leading to the identification of the maximum release considered for emergency preparedness planning (MREPP) scenario. The MREPP scenarios postulated were of three types: fire, tornado, and criticality. Fire was significant at oxide fuel fabrication, UF/sub 6/ production, radiopharmaceutical manufacturing, radiopharmacy, sealed source manufacturing, waste warehousing, and university research and development facilities. Tornadoes were MREPP events for uranium mills and plutonium contaminated facilities, and criticalities were significant at nonoxide fuel fabrication and nuclear research and development facilities. Techniques for adjusting the MREPP release to different facilities are also described.

  3. Nuclear Waste Materials Characterization Center. Semiannual progress report, April 1985-September 1985

    SciTech Connect (OSTI)

    Mendel, J.E.

    1985-12-01

    Work continued on converting MCC Quality Assurance practices to comply with the national QA standard for nuclear facilities, ANSI/ASME NQA-1. Support was provided to the following: Office of Geologic Repositories; Salt Repository Project; Basalt Waste Isolation Project; Office of Defense Waste and Byproducts Management; Hanford Programs; Transportation Technology Center; and West Valley Demonstration Project. (LM)

  4. Notice of Intent to Develop a Page Change for Department of Energy Order 474.2 Chg 3, Nuclear Material Control and Accountability

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2016-01-07

    The change will be limited in scope to correct language requiring the Office of Nuclear Materials Integration (ONMI) to be an approver for termination of safeguards for all sites.

  5. Finding of no significant impact. Consolidation and interim storage of special nuclear material at Rocky Flats Environmental Technology Site

    SciTech Connect (OSTI)

    1995-06-01

    The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA -- 1060, for the consolidation, processing, and interim storage of Category I and II special nuclear material (SNM) in Building 371 at the Rocky Flats Environmental Technology Site (hereinafter referred to as Rocky Flats or Site), Golden, Colorado. The scope of the EA included alternatives for interim storage including the no action alternative, the construction of a new facility for interim storage at Rocky Flats, and shipment to other DOE facilities for interim storage.

  6. Testing of nuclear grade lubricants and their effects on A540 B24 and A193 B7 bolting materials

    SciTech Connect (OSTI)

    Czajkowski, C.J.

    1985-01-01

    An investigation was performed on eleven commonly used lubricants by the nuclear power industry. The investigation included EDS analysis of the lubricants, notched-tensile constant extension rate testing of bolting materials with the lubricants, frictional testing of the lubricants and weight loss testing of a bonded solid film lubricant. The report generally concludes that there is a significant amount of variance in the mechanical properties of common bolting materials; that MoS/sub 2/ can hydrolyze to form H/sub 2/S at 100/sup 0/C and cause stress corrosion cracking (SCC) of bolting materials, and that the use of copper-containing lubricants can be potentially detrimental to high strength steels in an aqueous environment. Additionally, the testing of various lubricants disclosed that some lubricants contain potentially detrimental elements (e.g. S, Sb) which can promote SCC of the common bolting materials. One of the most significant findings of this report is the observation that both A193 B7 and A540 B24 bolting materials are susceptible to transgranular stress corrosion cracking in demineralized H/sub 2/O at 280/sup 0/C in notched tensile tests.

  7. Some Materials Degradation Issues in the U.S. High-Level Nuclear Waste Repository Study (The Yucca Mountain Project)

    SciTech Connect (OSTI)

    F. Hua; P. Pasupathi; N. Brown; K. Mon

    2005-09-19

    The safe disposal of radioactive waste requires that the waste be isolated from the environment until radioactive decay has reduced its toxicity to innocuous levels for plants, animals, and humans. All of the countries currently studying the options for disposing of high-level nuclear waste (HLW) have selected deep geologic formations to be the primary barrier for accomplishing this isolation. In U.S.A., the Nuclear Waste Policy Act of 1982 (as amended in 1987) designated Yucca Mountain in Nevada as the potential site to be characterized for high-level nuclear waste (HLW) disposal. Long-term containment of waste and subsequent slow release of radionuclides into the geosphere will rely on a system of natural and engineered barriers including a robust waste containment design. The waste package design consists of a highly corrosion resistant Ni-based Alloy 22 cylindrical barrier surrounding a Type 316 stainless steel inner structural vessel. The waste package is covered by a mailbox-shaped drip shield composed primarily of Ti Grade 7 with Ti Grade 24 structural support members. The U.S. Yucca Mountain Project has been studying and modeling the degradation issues of the relevant materials for some 20 years. This paper reviews the state-of-the-art understanding of the degradation processes based on the past 20 years studies on Yucca Mountain Project (YMP) materials degradation issues with focus on interaction between the in-drift environmental conditions and long-term materials degradation of waste packages and drip shields within the repository system during the 10,000 years regulatory period. This paper provides an overview of the current understanding of the likely degradation behavior of the waste package and drip shield in the repository after the permanent closure of the facility. The degradation scenario discussed in this paper include aging and phase instability, dry oxidation, general and localized corrosion, stress corrosion cracking and hydrogen induced cracking of Alloy 22 and titanium alloys. The effects of microbial activity and radiation on degradation of Alloy 22 and titanium alloys are also discussed. Further, for titanium alloys, the effects of fluorides, bromides, calcium ions, and galvanic coupling to less noble metals are further considered. It is concluded that, as far as materials degradation is concerned, the materials and design adopted in the U.S. Yucca Mountain Project will provide sufficient safety margins within the 10,000-years regulatory period.

  8. Validating mass spectrometry measurements of nuclear materials via a non-contact volume analysis method of ion sputter craters

    SciTech Connect (OSTI)

    Willingham, David G.; Naes, Benjamin E.; Fahey, Albert J.

    2015-01-01

    A combination of secondary ion mass spectrometry, optical profilometry and a statistically-driven algorithm was used to develop a non-contact volume analysis method to validate the useful yields of nuclear materials. The volume analysis methodology was applied to ion sputter craters created in silicon and uranium substrates sputtered by 18.5 keV O- and 6.0 keV Ar+ ions. Sputter yield measurements were determined from the volume calculations and were shown to be comparable to Monte Carlo calculations and previously reported experimental observations. Additionally, the volume calculations were used to determine the useful yields of Si+, SiO+ and SiO2+ ions from the silicon substrate and U+, UO+ and UO2+ ions from the uranium substrate under 18.5 keV O- and 6.0 keV Ar+ ion bombardment. This work represents the first steps toward validating the interlaboratory and cross-platform performance of mass spectrometry for the analysis of nuclear materials.

  9. Ultra-low field nuclear magnetic resonance and magnetic resonance imaging to discriminate and identify materials

    DOE Patents [OSTI]

    Matlashov, Andrei Nikolaevich; Urbaitis, Algis V.; Savukov, Igor Mykhaylovich; Espy, Michelle A.; Volegov, Petr Lvovich; Kraus, Jr., Robert Henry

    2013-03-05

    Method comprising obtaining an NMR measurement from a sample wherein an ultra-low field NMR system probes the sample and produces the NMR measurement and wherein a sampling temperature, prepolarizing field, and measurement field are known; detecting the NMR measurement by means of inductive coils; analyzing the NMR measurement to obtain at least one measurement feature wherein the measurement feature comprises T1, T2, T1.rho., or the frequency dependence thereof; and, searching for the at least one measurement feature within a database comprising NMR reference data for at least one material to determine if the sample comprises a material of interest.

  10. Ultra-low field nuclear magnetic resonance and magnetic resonance imaging to discriminate and identify materials

    DOE Patents [OSTI]

    Kraus, Robert H.; Matlashov, Andrei N.; Espy, Michelle A.; Volegov, Petr L.

    2010-03-30

    An ultra-low magnetic field NMR system can non-invasively examine containers. Database matching techniques can then identify hazardous materials within the containers. Ultra-low field NMR systems are ideal for this purpose because they do not require large powerful magnets and because they can examine materials enclosed in conductive shells such as lead shells. The NMR examination technique can be combined with ultra-low field NMR imaging, where an NMR image is obtained and analyzed to identify target volumes. Spatial sensitivity encoding can also be used to identify target volumes. After the target volumes are identified the NMR measurement technique can be used to identify their contents.

  11. 2013 Annual DOE-NE Materials Research Coordination Meeting | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Energy Annual DOE-NE Materials Research Coordination Meeting 2013 Annual DOE-NE Materials Research Coordination Meeting The Reactor Materials element of the Nuclear Energy Enabling Technologies (NEET) program conducted its FY 2013 coordination meeting as a series of four web-conferences to act as a forum for the nuclear materials research community. The purpose of this meeting was to report on current and planned nuclear materials research, identify new areas of collaboration and promote

  12. 2015 ANNUAL DOE-NE MATERIALS RESEARCH MEETING | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    ANNUAL DOE-NE MATERIALS RESEARCH MEETING 2015 ANNUAL DOE-NE MATERIALS RESEARCH MEETING The Reactor Materials element of the Nuclear Energy Enabling Technologies (NEET) program conducted its FY 2015 coordination meeting as a series of two web-conferences to act as a forum for the nuclear materials research community. The purpose of this meeting was to report on current and planned nuclear materials research, identify new areas of collaboration and promote greater coordination among the various

  13. Non-Contact Measurement of Thermal Diffusivity in Ion-Implanted Nuclear Materials

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Hofmann, F.; Mason, D. R.; Eliason, J. K.; Maznev, A. A.; Nelson, K. A.; Dudarev, S. L.

    2015-11-03

    Knowledge of mechanical and physical property evolution due to irradiation damage is essential for the development of future fission and fusion reactors. Ion-irradiation provides an excellent proxy for studying irradiation damage, allowing high damage doses without sample activation. Limited ion-penetration-depth means that only few-micron-thick damaged layers are produced. Substantial effort has been devoted to probing the mechanical properties of these thin implanted layers. Yet, whilst key to reactor design, their thermal transport properties remain largely unexplored due to a lack of suitable measurement techniques. Here we demonstrate non-contact thermal diffusivity measurements in ion-implanted tungsten for nuclear fusion armour. Alloying withmore » transmutation elements and the interaction of retained gas with implantation-induced defects both lead to dramatic reductions in thermal diffusivity. These changes are well captured by our modelling approaches. Our observations have important implications for the design of future fusion power plants.« less

  14. 105-K Basin material design basis feed description for spent nuclear fuel project facilities

    SciTech Connect (OSTI)

    Praga, A.N.

    1998-01-08

    Revisions 0 and 0A of this document provided estimated chemical and radionuclide inventories of spent nuclear fuel and sludge currently stored within the Hanford Site`s 105-K Basins. This Revision (Rev. 1) incorporates the following changes into Revision 0A: (1) updates the tables to reflect: improved cross section data, a decision to use accountability data as the basis for total Pu, a corrected methodology for selection of the heat generation basis fee, and a revised decay date; (2) adds section 3.3.3.1 to expand the description of the approach used to calculate the inventory values and explain why that approach yields conservative results; (3) changes the pre-irradiation braze beryllium value.

  15. Non-Contact Measurement of Thermal Diffusivity in Ion-Implanted Nuclear Materials

    SciTech Connect (OSTI)

    Hofmann, F.; Mason, D. R.; Eliason, J. K.; Maznev, A. A.; Nelson, K. A.; Dudarev, S. L.

    2015-11-03

    Knowledge of mechanical and physical property evolution due to irradiation damage is essential for the development of future fission and fusion reactors. Ion-irradiation provides an excellent proxy for studying irradiation damage, allowing high damage doses without sample activation. Limited ion-penetration-depth means that only few-micron-thick damaged layers are produced. Substantial effort has been devoted to probing the mechanical properties of these thin implanted layers. Yet, whilst key to reactor design, their thermal transport properties remain largely unexplored due to a lack of suitable measurement techniques. Here we demonstrate non-contact thermal diffusivity measurements in ion-implanted tungsten for nuclear fusion armour. Alloying with transmutation elements and the interaction of retained gas with implantation-induced defects both lead to dramatic reductions in thermal diffusivity. These changes are well captured by our modelling approaches. Our observations have important implications for the design of future fusion power plants.

  16. Corrosion and environmental-mechanical characterization of iron-base nuclear waste package structural barrier materials. Annual report, FY 1984

    SciTech Connect (OSTI)

    Westerman, R.E.; Haberman, J.H.; Pitman, S.G.; Pulsipher, B.A.; Sigalla, L.A.

    1986-03-01

    Disposal of high-level nuclear waste in deep underground repositories may require the development of waste packages that will keep the radioisotopes contained for up to 1000 y. A number of iron-base materials are being considered for the structural barrier members of waste packages. Their uniform and nonuniform (pitting and intergranular) corrosion behavior and their resistance to stress-corrosion cracking in aqueous environments relevant to salt media are under study at Pacific Northwest Laboratory. The purpose of the work is to provide data for a materials degradation model that can ultimately be used to predict the effective lifetime of a waste package overpack in the actual repository environment. The corrosion behavior of the candidate materials was investigated in simulated intrusion brine (essentially NaCl) in flowing autoclave tests at 150/sup 0/C, and in combinations of intrusion/inclusion (high-Mg) brine environments in moist salt tests, also at 150/sup 0/C. Studies utilizing a /sup 60/Co irradiation facility were performed to determine the corrosion resistance of the candidate materials to products of brine radiolysis at dose rates of 2 x 10/sup 3/ and 1 x 10/sup 5/ rad/h and a temperature of 150/sup 0/C. These irradiation-corrosion tests were ''overtests,'' as the irradiation intensities employed were 10 to 1000 times as high as those expected at the surface of a thick-walled waste package. With the exception of the high general corrosion rates found in the tests using moist salt containing high-Mg brines, the ferrous materials exhibited a degree of corrosion resistance that indicates a potentially satisfactory application to waste package structural barrier members in a salt repository environment.

  17. Uncertainty Quantification and Management for Multi-scale Nuclear Materials Modeling

    SciTech Connect (OSTI)

    McDowell, David; Deo, Chaitanya; Zhu, Ting; Wang, Yan

    2015-10-21

    Understanding and improving microstructural mechanical stability in metals and alloys is central to the development of high strength and high ductility materials for cladding and cores structures in advanced fast reactors. Design and enhancement of radiation-induced damage tolerant alloys are facilitated by better understanding the connection of various unit processes to collective responses in a multiscale model chain, including: dislocation nucleation, absorption and desorption at interfaces; vacancy production, radiation-induced segregation of Cr and Ni at defect clusters (point defect sinks) in BCC Fe-Cr ferritic/martensitic steels; investigation of interaction of interstitials and vacancies with impurities (V, Nb, Ta, Mo, W, Al, Si, P, S); time evolution of swelling (cluster growth) phenomena of irradiated materials; and energetics and kinetics of dislocation bypass of defects formed by interstitial clustering and formation of prismatic loops, informing statistical models of continuum character with regard to processes of dislocation glide, vacancy agglomeration and swelling, climb and cross slip.

  18. Application of Two Phase (Liquid/Gas) Xenon Gamma-Camera for the Detection of Special Nuclear Material and PET Medical Imaging

    SciTech Connect (OSTI)

    McKinsey, Daniel Nicholas

    2013-08-27

    The McKinsey group at Yale has been awarded a grant from DTRA for the building of a Liquid Xenon Gamma Ray Color Camera (LXe-GRCC), which combines state-of-the-art detection of LXe scintillation light and time projection chamber (TPC) charge readout. The DTRA application requires a movable detector and hence only a single phase (liquid) xenon detector can be considered in this case. We propose to extend the DTRA project to applications that allow a two phase (liquid/gas) xenon TPC. This entails additional (yet minimal) hardware and extension of the research effort funded by DTRA. The two phase detector will have better energy and angular resolution. Such detectors will be useful for PET medical imaging and detection of special nuclear material in stationary applications (e.g. port of entry). The expertise of the UConn group in gas phase TPCs will enhance the capabilities of the Yale group and the synergy between the two groups will be very beneficial for this research project as well as the education and research projects of the two universities. The LXe technology to be used in this project has matured rapidly over the past few years, developed for use in detectors for nuclear physics and astrophysics. This technology may now be applied in a straightforward way to the imaging of gamma rays. According to detailed Monte Carlo simulations recently performed at Yale University, energy resolution of 1% and angular resolution of 3 degrees may be obtained for 1.0 MeV gamma rays, using existing technology. With further research and development, energy resolution of 0.5% and angular resolution of 1.3 degrees will be possible at 1.0 MeV. Because liquid xenon is a high density, high Z material, it is highly efficient for scattering and capturing gamma rays. In addition, this technology scales elegantly to large detector areas, with several square meter apertures possible. The Yale research group is highly experienced in the development and use of noble liquid detectors for astrophysics, most recently in the XENON10 experiment. The existing facilities at Yale are fully adequate for the completion of this project. The facilities of the UConn group at the LNS at Avery Point include a (clean) lab for detector development and this group recently delivered an Optical Readout TPC (O-TPC) for research in Nuclear Astrophysics at the TUNL in Duke University. The machine shop at UConn will be used (free of charge) for producing the extra hardware needed for this project including grids and frames.

  19. Nuclear power plant cable materials : review of qualification and currently available aging data for margin assessments in cable performance.

    SciTech Connect (OSTI)

    Celina, Mathias Christopher; Gillen, Kenneth Todd; Lindgren, Eric Richard

    2013-05-01

    A selective literature review was conducted to assess whether currently available accelerated aging and original qualification data could be used to establish operational margins for the continued use of cable insulation and jacketing materials in nuclear power plant environments. The materials are subject to chemical and physical degradation under extended radiationthermal- oxidative conditions. Of particular interest were the circumstances under which existing aging data could be used to predict whether aged materials should pass loss of coolant accident (LOCA) performance requirements. Original LOCA qualification testing usually involved accelerated aging simulations of the 40-year expected ambient aging conditions followed by a LOCA simulation. The accelerated aging simulations were conducted under rapid accelerated aging conditions that did not account for many of the known limitations in accelerated polymer aging and therefore did not correctly simulate actual aging conditions. These highly accelerated aging conditions resulted in insulation materials with mostlyinert' aging processes as well as jacket materials where oxidative damage dropped quickly away from the air-exposed outside jacket surface. Therefore, for most LOCA performance predictions, testing appears to have relied upon heterogeneous aging behavior with oxidation often limited to the exterior of the cable cross-section - a situation which is not comparable with the nearly homogenous oxidative aging that will occur over decades under low dose rate and low temperature plant conditions. The historical aging conditions are therefore insufficient to determine with reasonable confidence the remaining operational margins for these materials. This does not necessarily imply that the existing 40-year-old materials would fail if LOCA conditions occurred, but rather that unambiguous statements about the current aging state and anticipated LOCA performance cannot be provided based on original qualification testing data alone. The non-availability of conclusive predictions for the aging conditions of 40-year-old cables implies that the same levels of uncertainty will remain for any re-qualification or extended operation of these cables. The highly variable aging behavior of the range of materials employed also implies that simple, standardized aging tests are not sufficient to provide the required aging data and performance predictions for all materials. It is recommended that focused studies be conducted that would yield the material aging parameters needed to predict aging behaviors under low dose, low temperature plant equivalent conditions and that appropriately aged specimens be prepared that would mimic oxidatively-aged 40- to 60- year-old materials for confirmatory LOCA performance testing. This study concludes that it is not sufficient to expose materials to rapid, high radiation and high temperature levels with subsequent LOCA qualification testing in order to predictively quantify safety margins of existing infrastructure with regard to LOCA performance. We need to better understand how cable jacketing and insulation materials have degraded over decades of power plant operation and how this aging history relates to service life prediction and the performance of existing equipment to withstand a LOCA situation.

  20. A system for the measurement of delayed neutrons and gammas from special nuclear materials

    SciTech Connect (OSTI)

    Andrews, M. T.; Corcoran, E. C.; Goorley, J. T.; Kelly, D. G.

    2014-11-27

    The delayed neutron counting (DNC) system at the Royal Military College of Canada has been upgraded to accommodate concurrent delayed neutron and gamma measurements. This delayed neutron and gamma counting (DNGC) system uses a SLOWPOKE-2 reactor to irradiate fissile materials before their transfer to a counting arrangement consisting of six He and one HPGe detector. The application of this system is demonstrated in an example where delayed neutron and gamma emissions are used in complement to examine U content and determine fissile mass with an average relative error and accuracy of -2.2 and 1.5 %, respectively.

  1. A system for the measurement of delayed neutrons and gammas from special nuclear materials

    DOE Public Access Gateway for Energy & Science Beta (PAGES Beta)

    Andrews, M. T.; Corcoran, E. C.; Goorley, J. T.; Kelly, D. G.

    2014-11-27

    The delayed neutron counting (DNC) system at the Royal Military College of Canada has been upgraded to accommodate concurrent delayed neutron and gamma measurements. This delayed neutron and gamma counting (DNGC) system uses a SLOWPOKE-2 reactor to irradiate fissile materials before their transfer to a counting arrangement consisting of six ³He and one HPGe detector. The application of this system is demonstrated in an example where delayed neutron and gamma emissions are used in complement to examine ²³³U content and determine fissile mass with an average relative error and accuracy of -2.2 and 1.5 %, respectively.

  2. Approach to IAEA verification of the nuclear-material balance at the Portsmouth Gas Centrifuge Enrichment Plant (GCEP)

    SciTech Connect (OSTI)

    Gordon, D.M.; Sanborn, J.B.; Younkin, J.M.; DeVito, V.J.

    1982-01-01

    This paper describes a potential approach by which the International Atomic Energy Agency (IAEA) might verify the nuclear-material balance at the Portsmouth Gas Centrifuge Enrichment Plant (GCEP), should that plant be placed under IAEA safeguards. The strategy makes use of the attributes and variables measurement verification approach, whereby the IAEA would perform independent measurements on a randomly selected subset of the items comprising the U-235 flows and inventories at the plant. In addition, the MUF-D statistic is used as the test statistics for the detection of diversion. The paper includes descriptions of the potential verification activities, as well as calculations of (a) attributes and variables sample sizes for the various strata, (b) standard deviations of the relevant test statistics, and (c) the sensitivity for detection of diversion which the IAEA might achieve by this verification strategy at GCEP.

  3. NRC - regulator of nuclear safety

    SciTech Connect (OSTI)

    1997-05-01

    The U.S. Nuclear Regulatory Commission (NRC) was formed in 1975 to regulate the various commercial and institutional uses of nuclear energy, including nuclear power plants. The agency succeeded the Atomic Energy Commission, which previously had responsibility for both developing and regulating nuclear activities. Federal research and development work for all energy sources, as well as nuclear weapons production, is now conducted by the U.S. Department of Energy. Under its responsibility to protect public health and safety, the NRC has three principal regulatory functions: (1) establish standards and regulations, (2) issue licenses for nuclear facilities and users of nuclear materials, and (3) inspect facilities and users of nuclear materials to ensure compliance with the requirements. These regulatory functions relate to both nuclear power plants and to other uses of nuclear materials - like nuclear medicine programs at hospitals, academic activities at educational institutions, research work, and such industrial applications as gauges and testing equipment. The NRC places a high priority on keeping the public informed of its work. The agency recognizes the interest of citizens in what it does through such activities as maintaining public document rooms across the country and holding public hearings, public meetings in local areas, and discussions with individuals and organizations.

  4. Materials Degradation Issues in the U.S. High-Level Nuclear Waste Repository

    SciTech Connect (OSTI)

    K.G. Mon; F. Hua

    2005-04-12

    This paper reviews the state-of-the-art understanding of the degradation processes by the Yucca Mountain Project (YMP) with focus on interaction between the in-drift environmental conditions and long-term materials degradation of waste packages and drip shields within the repository system during the first 10,000-years after repository closure. This paper provides an overview of the degradation of the waste packages and drip shields in the repository after permanent closure of the facility. The degradation modes discussed in this paper include aging and phase instability, dry oxidation, general and localized corrosion, stress corrosion cracking, and hydrogen induced cracking of Alloy 22 and titanium alloys. The effects of microbial activity and radiation on the degradation of Alloy 22 and titanium alloys are also discussed. Further, for titanium alloys, the effects of fluorides, bromides, and galvanic coupling to less noble metals are considered. It is concluded that the materials and design adopted will provide sufficient safety margins for at least 10,000-years after repository closure.

  5. Report on Follow-up Inspection of the Double Funding of Security for Special Nuclear Material at Richland Operations, IG-0378

    Energy Savers [EERE]

    1 INFORMATION: Report on "Follow-up Inspection of the Double Funding of Security for Special Nuclear Material at the Richland Operations Office" The Secretary BACKGROUND: On June 3, 1993, the Deputy Assistant Inspector General for Inspections issued a Letter Report to the Department's Acting Chief Financial Officer which stated that during Fiscal Year 1993 the Department had requested and received $60 million, double the funding needed, for the safeguard and security of special nuclear

  6. The Project Shoal Area (PSA), located about 50 km southeast of Fallon, Nevada, was the site for a 12-kiloton-ton nuclear test

    Office of Legacy Management (LM)

    NV/13609-53 Development of a Groundwater Management Model for the Project Shoal Area prepared by Gregg Lamorey, Scott Bassett, Rina Schumer, Douglas P. Boyle, Greg Pohll, and Jenny Chapman submitted to Nevada Site Office National Nuclear Security Administration U.S. Department of Energy Las Vegas, Nevada September 2006 Publication No. 45223 Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily

  7. A Water Balance Study of Four Landfill Cover Designs at Material Disposal Area B in Los Alamos, New Mexico

    SciTech Connect (OSTI)

    David D. Breshears; Fairley J. Barnes; John W. Nyhan; Johnny A. Salazar

    1998-09-01

    The goal of disposing of low-level radioactive and hazardous waste in shallow landfills is to reduce risk to human health and the environment by isolating contaminants until they no longer pose an unacceptable hazard. In order to achieve this, the Department of Energy Environmental Restoration Program is comparing the performance of several different surface covers at Material Disposal Area (MDA) B in Los Alamos. Two conventional landfill were compared with an improved cover designed to minimize plant and animal intrusion and to minimize water infiltration into the underlying wastes. The conventional covers varied in depth and both conventional and improved designs had different combinations of vegetation (grass verses shrub) and gravel mulch (no mulch verses mulch). These treatments were applied to each of 12 plots and water balance parameters were measured from March1987 through June 1995. Adding a gravel mulch significantly influenced the plant covered field plots receiving no gravel mulch averaged 21.2% shrub cover, while plots with gravel had a 20% larger percent cover of shrubs. However, the influence of gravel mulch on the grass cover was even larger than the influence on shrub cover, average grass cover on the plots with no gravel was 16.3%, compared with a 42% increase in grass cover due to gravel mulch. These cover relationships are important to reduce runoff on the landfill cover, as shown by a regression model that predicts that as ground cover is increased from 30 to 90%,annual runoff is reduced from 8.8 to 0.98 cm-a nine-fold increase. We also found that decreasing the slope of the landfill cover from 6 to 2% reduced runoff from the landfill cover by 2.7-fold. To minimize the risk of hazardous waste from landfills to humans, runoff and seepage need to be minimized and evapotranspiration maximized on the landfill cover. This has to be accomplished for dry and wet years at MDA B. Seepage consisted of 1.9% and 6.2% of the precipitation in the average and once in ten year events, respectively, whereas corresponding values for runoff were 13% and 16%; these changes were accompanied by corresponding decreases in evapotranspiration, which accounted for 86% and only 78% of the precipitation occurring on the average and once in ten year even~ respectively.

  8. Thermal performance sensitivity studies in support of material modeling for extended storage of used nuclear fuel

    SciTech Connect (OSTI)

    Cuta, Judith M.; Suffield, Sarah R.; Fort, James A.; Adkins, Harold E.

    2013-08-15

    The work reported here is an investigation of the sensitivity of component temperatures of a storage system, including fuel cladding temperatures, in response to age-related changes that could degrade the design-basis thermal behavior of the system. Three specific areas of interest were identified for this study. degradation of the canister backfill gas from pure helium to a mixture of air and helium, resulting from postulated leakage due to stress corrosion cracking (SCC) of canister welds changes in surface emissivity of system components, resulting from corrosion or other aging mechanisms, which could cause potentially significant changes in temperatures and temperature distributions, due to the effect on thermal radiation exchange between components changes in fuel and basket temperatures due to changes in fuel assembly position within the basket cells in the canister The purpose of these sensitivity studies is to provide a realistic example of how changes in the physical properties or configuration of the storage system components can affect temperatures and temperature distributions. The magnitudes of these sensitivities can provide guidance for identifying appropriate modeling assumptions for thermal evaluations extending long term storage out beyond 50, 100, 200, and 300 years.

  9. Materials and Molecular Research Division annual report 1980

    SciTech Connect (OSTI)

    Not Available

    1981-06-01

    Progress made in the following research areas is reported: materials sciences (metallurgy and ceramics, solid state physics, materials chemistry); chemical sciences (fundamental interactions, processes and techniques); nuclear sciences; fossil energy; advanced isotope separation technology; energy storage; magnetic fusion energy; and nuclear waste management.

  10. material recovery

    National Nuclear Security Administration (NNSA)

    dispose of dangerous nuclear and radiological material, and detect and control the proliferation of related WMD technology and expertise.

  11. Nuclear Energy Plant Optimization (NEPO) final report on aging and condition monitoring of low-voltage cable materials.

    SciTech Connect (OSTI)

    Assink, Roger Alan; Gillen, Kenneth Todd; Bernstein, Robert

    2005-11-01

    This report summarizes results generated on a 5-year cable-aging program that constituted part of the Nuclear Energy Plant Optimization (NEPO) program, an effort cosponsored by the U. S. Department of Energy (DOE) and the Electric Power Research Institute (EPRI). The NEPO cable-aging effort concentrated on two important issues involving the development of better lifetime prediction methods as well as the development and testing of novel cable condition-monitoring (CM) techniques. To address improved life prediction methods, we first describe the use of time-temperature superposition principles, indicating how this approach improves the testing of the Arrhenius model by utilizing all of the experimentally generated data instead of a few selected and processed data points. Although reasonable superposition is often found, we show several cases where non-superposition is evident, a situation that violates the constant acceleration assumption normally used in accelerated aging studies. Long-term aging results over extended temperature ranges allow us to show that curvature in Arrhenius plots for elongation is a common occurrence. In all cases the curvature results in a lowering of the Arrhenius activation energy at lower temperatures implying that typical extrapolation of high temperature results over-estimates material lifetimes. The long-term results also allow us to test the significance of extrapolating through the crystalline melting point of semi-crystalline materials. By utilizing ultrasensitive oxygen consumption (UOC) measurements, we show that it is possible to probe the low temperature extrapolation region normally inaccessible to conventional accelerated aging studies. This allows the quantitative testing of the often-used Arrhenius extrapolation assumption. Such testing indicates that many materials again show evidence of ''downward'' curvature (E{sub a} values drop as the aging temperature is lowered) consistent with the limited elongation results and many literature results. It is also shown how the UOC approach allows the probing of temperatures that cross through the crystalline melting point region of semi-crystalline materials such as XLPO and EPR cable insulations. New results on combined environment aging of neoprene and hypalon cable jacketing materials are presented and offer additional evidence in support of our time-temperature-dose rate (t-T-DR) superposition approach that had been used successfully in the past for such situations.

  12. An Aerial Radiological survey of the Alvin W. Vogtle Nuclear Plant and surrounding area, Waynesboro, Georgia: Date of survey: August--September 1988

    SciTech Connect (OSTI)

    Not Available

    1990-09-01

    An Aerial Radiological Survey was conducted during the period of August 24 to September 14, 1988 over an area of approximately 310 square kilometers (120 square miles) surrounding the Alvin W. Vogtle Nuclear Plant. The Vogtle Nuclear Plant is located near Augusta, Georgia, along the Savannah River and adjacent to the Savannah River Site (SRS). Several anomalous areas were identified in the portion of the survey extending into the SRS perimeter. The dominant isotopes found in these areas were cesium-137 and cobalt-60. All of these man-made anomalies identified by the aerial measurements were attributed to SRS processing. For the remainder of the survey area, the inferred radiation exposure rates generally varied from 6 to 10 microroentgens per hour ({mu}R/h), which was found to be due to naturally occurring uranium, thorium, and radioactive potassium gamma emitters. The reported exposure rate values included an estimated cosmic ray contribution of 3.6 {mu}R/h. Soils samples and pressurized ion chamber measurements were obtained at three locations within the survey boundaries to support the aerial data. The exposure rate values obtained from these groundbased measurements were in agreement with the corresponding inferred aerial values. 6 refs., 13 figs., 4 tabs.

  13. Advanced nuclear fuel

    SciTech Connect (OSTI)

    Terrani, Kurt

    2014-07-14

    Kurt Terrani uses his expertise in materials science to develop safer fuel for nuclear power plants.

  14. Advanced nuclear fuel

    ScienceCinema (OSTI)

    Terrani, Kurt

    2014-07-15

    Kurt Terrani uses his expertise in materials science to develop safer fuel for nuclear power plants.

  15. A Cultural Resources Inventory and Historical Evaluation of the Smoky Atmospheric Nuclear Test, Areas 8, 9, and 10, Nevada National Security Site, Nye County, Nevada

    SciTech Connect (OSTI)

    Jones, Robert C.; King, Maureen L.; Beck, Colleen M.; Falvey, Lauren W.; Menocal, Tatianna M.

    2014-09-01

    This report presents the results of a National Historic Preservation Act Section 106 cultural resources inventory and historical evaluation of the 1957 Smoky atmospheric test location on the Nevada National Security Site (NNSS). The Desert Research Institute (DRI) was tasked to conduct a cultural resources study of the Smoky test area as a result of a proposed undertaking by the Department of Energy Environmental Management. This undertaking involves investigating Corrective Action Unit (CAU) 550 for potential contaminants of concern as delineated in a Corrective Action Investigation Plan. CAU 550 is an area that spatially overlaps portions of the Smoky test location. Smoky, T-2c, was a 44 kt atmospheric nuclear test detonated at 5:30 am on August 31, 1957, on top of a 213.4 m (700 ft) 200 ton tower (T-2c) in Area 8 of the NNSS. Smoky was a weapons related test of the Plumbbob series (number 19) and part of the Department of Defense Exercise Desert Rock VII and VIII. The cultural resources effort involved the development of a historic context based on archival documents and engineering records, the inventory of the cultural resources in the Smoky test area and an associated military trench location in Areas 9 and 10, and an evaluation of the National Register eligibility of the cultural resources. The inventory of the Smoky test area resulted in the identification of structures, features, and artifacts related to the physical development of the test location and the post-test remains. The Smoky test area was designated historic district D104 and coincides with a historic archaeological site recorded as 26NY14794 and the military trenches designed for troop observation, site 26NY14795. Sites 26NY14794 and 26NY14795 are spatially discrete with the trenches located 4.3 km (2.7 mi) southeast of the Smoky ground zero. As a result, historic district D104 is discontiguous and in total it covers 151.4 hectares (374 acres). The Smoky test location, recorded as historic district D104 and historic sites 26NY14794 and 26NY14795, is the best preserved post-shot atmospheric nuclear tower test at the NNSS and possibly in the world. It is of local, national, and international importance due to nuclear testing’s pivotal role in the Cold War between the United States and the former Soviet Union. The district and sites are linked to the historic theme of atmospheric nuclear testing. D104 retains aspects of the engineering plan and design for the Smoky tower, instrument stations used to measure test effects, German and French personnel shelters, and military trenches. A total of 33 structures contribute to the significance of D104. Artifacts and features provide significant post-test information. Historic district D104 (discontiguous) and historic site 26NY14794 (the Smoky test area) are eligible for listing on the NRHP under Criteria A, B, C, and D. The historic site 26NY14795 (the Smoky military trenches) is eligible for listing under Criteria A, C, and D. Several items have been identified for removal by the CAU 550 investigation. However, none of them is associated with the Smoky atmospheric test, but with later activities in the area. The military trenches are not part of CAU 550 and no actions are planned there. A proposed closure of the Smoky test area with restrictions will limit access and contribute to the preservation of the cultural resources. It is recommended that the Smoky historic district and sites be included in the NNSS cultural resources monitoring program.

  16. Material Protection, Accounting and Control

    Office of Environmental Management (EM)

    Overview and Advanced Instrumentation Development Michael Miller, Ph.D. National Technical Director Los Alamos National Laboratory Instrumentation and Control Review Meeting September 17, 2014 LA-UR-14-27347 2 Introduction September 17, 2014 n Preventing, deterring, and detecting misuse of nuclear materials and associated fuel cycle technologies is of paramount concern to both national and global security. Success in this area is critical for the existing and future nuclear energy enterprise.

  17. Background studies in support of a feasibility assessment on the use of copper-base materials for nuclear waste packages in a repository in tuff

    SciTech Connect (OSTI)

    Van Konynenburg, R.A.; Kundig, K.J.A.; Lyman, W.S.; Prager, M.; Meyers, J.R.; Servi, I.S.

    1990-06-01

    This report combines six work units performed in FY`85--86 by the Copper Development Association and the International Copper Research Association under contract with the University of California. The work includes literature surveys and state-of-the-art summaries on several considerations influencing the feasibility of the use of copper-base materials for fabricating high-level nuclear waste packages for the proposed repository in tuff rock at Yucca Mountain, Nevada. The general conclusion from this work was that copper-base materials are viable candidates for inclusion in the materials selection process for this application. 55 refs., 48 figs., 22 tabs.

  18. Regulatory Guide 5.29, Revision 2, "Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants".

    National Nuclear Security Administration (NNSA)

    NUCLEAR REGULATORY COMMISSION June 2013 Revision 2 REGULATORY GUIDE OFFICE OF NUCLEAR REGULATORY RESEARCH Written suggestions regarding this guide or development of new guides may be submitted through the NRC's public Web site under the Regulatory Guides document collection of the NRC Library at http://www.nrc.gov/reading-rm/doc-collections/reg-guides/contactus.html. Electronic copies of this regulatory guide, previous versions of this guide, and other recently issued guides are available

  19. Nuclear Material Disposition

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2015-12-18

    This Guide describes acceptable, but not mandatory means for complying with requirements. Guides are not requirements documents and are not to be construed as requirements in any audit or appraisal for compliance with associated rule or directives.

  20. CASL - Materials and Performance Optimization (MPO)

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Materials and Performance Optimization (MPO) The Materials and Performance Optimization (MPO) focus area within CASL has recently developed and released a 3D modeling framework known as MAMBA (MPO Advanced Model for Boron Analysis) to predict CRUD deposition on nuclear fuel rods. CRUD, which refers to Chalk River Unidentified Deposit, is predominately a nickel-ferrite spinel corrosion product that deposits on hot fuel clad surfaces in nuclear reactors. CRUD has a lower thermal conductivity than

  1. Implementing Arrangement Between the U.S. Department of Energy and the Department of Natural Resources of Canada and Atomic Energy of Canada Limited For Collaboration in the Area of Nuclear Research

    Broader source: Energy.gov [DOE]

    Implementing Arrangement Between the U.S. Department of Energy and the Department of Natural Resources of Canada and Atomic Energy of Canada Limited For Collaboration in the Area of Nuclear Research

  2. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 2

    SciTech Connect (OSTI)

    NONE

    1988-01-01

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site; to describe the conceptual designs for the repository and the waste package and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. Chapter 3 summarizes present knowledge of the regional and site hydrologic systems. The purpose of the information presented is to (1) describe the hydrology based on available literature and preliminary site-exploration activities that have been or are being performed and (2) provide information to be used to develop the hydrologic aspects of the planned site characterization program. Chapter 4 contains geochemical information about the Yucca Mountain site. The chapter references plan for continued collection of geochemical data as a part of the site characterization program. Chapter 4 describes and evaluates data on the existing climate and site meterology, and outlines the suggested procedures to be used in developing and validating methods to predict future climatic variation. 534 refs., 100 figs., 72 tabs.

  3. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 7

    SciTech Connect (OSTI)

    1988-01-01

    The Yucca Mountain site in Neavada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended and approved for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package;and to present the plans for obtaining hte geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare and environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed.

  4. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 1

    SciTech Connect (OSTI)

    1988-01-01

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in acordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and eveloping a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing prinicples, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed. 880 refs., 130 figs., 25 tabs.

  5. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act

    SciTech Connect (OSTI)

    1988-01-01

    Chapter six describes the basis for facility design, the completed facility conceptual design, the completed analytical work relating to the resolution of design issues, and future design-related work. The basis for design and the conceptual design information presented in this chapter meet the requirements of the Nuclear Waste Policy Act of 1982, for a conceptual repository design that takes into account site-specific requirements. This information is presented to permit a critical evaluation of planned site characterization activities. Chapter seven describes waste package components, emplacement environment, design, and status of research and development that support the Nevada Nuclear Waste Storage Investigation (NNWSI) Project. The site characterization plan (SCP) discussion of waste package components is contained entirely within this chapter. The discussion of emplacement environment in this chapter is limited to considerations of the environment that influence, or which may influence, if perturbed, the waste packages and their performance (particularly hydrogeology, geochemistry, and borehole stability). The basis for conceptual waste package design as well as a description of the design is included in this chapter. The complete design will be reported in the advanced conceptual design (ACD) report and is not duplicated in the SCP. 367 refs., 173 figs., 68 tabs.

  6. Reactor Materials Newsletter- Issue 1

    Broader source: Energy.gov [DOE]

    The Reactor Materials (RM) newsletter includes information about key nuclear materials programs, results from ongoing projects across the Office of Nuclear Energy, and other relevant information.

  7. High Risk Material Studies

    Broader source: Energy.gov [DOE]

    Spent Fuel Working Group Report on inventory and storage of the Department's spent nuclear fuel and other reactor irradiated nuclear materials and their environmental, safety and health vulnerabilities.

  8. Corrosion of aluminum clad spent nuclear fuel in the 70 ton cask during transfer from L area to H-canyon

    SciTech Connect (OSTI)

    Mickalonis, J. I.

    2015-08-01

    Aluminum-clad spent nuclear fuel will be transported for processing in the 70-ton nuclear fuel element cask from L Basin to H-canyon. During transport these fuels would be expected to experience high temperature aqueous corrosion from the residual L Basin water that will be present in the cask. Cladding corrosion losses during transport were calculated for material test reactor (MTR) and high flux isotope reactors (HFIR) fuels using literature and site information on aqueous corrosion at a range of time/temperature conditions. Calculations of the cladding corrosion loss were based on Arrhenius relationships developed for aluminum alloys typical of cladding material with the primary assumption that an adherent passive film does not form to retard the initial corrosion rate. For MTR fuels a cladding thickness loss of 33% was found after 1 year in the cask with a maximum temperature of 263 °C. HFIR fuels showed a thickness loss of only 6% after 1 year at a maximum temperature of 180 °C. These losses are not expected to impact the overall confinement function of the aluminum cladding.

  9. Corrosion of aluminum clad spent nuclear fuel in the 70 ton cask during transfer from L area to H-canyon

    SciTech Connect (OSTI)

    Mickalonis, J. I.

    2015-08-31

    Aluminum-clad spent nuclear fuel will be transported for processing in the 70-ton nuclear fuel element cask from L Basin to H-canyon. During transport these fuels would be expected to experience high temperature aqueous corrosion from the residual L Basin water that will be present in the cask. Cladding corrosion losses during transport were calculated for material test reactor (MTR) and high flux isotope reactors (HFIR) fuels using literature and site information on aqueous corrosion at a range of time/temperature conditions. Calculations of the cladding corrosion loss were based on Arrhenius relationships developed for aluminum alloys typical of cladding material with the primary assumption that an adherent passive film does not form to retard the initial corrosion rate. For MTR fuels a cladding thickness loss of 33 % was found after 1 year in the cask with a maximum temperature of 263 °C. HFIR fuels showed a thickness loss of only 6% after 1 year at a maximum temperature of 180 °C. These losses are not expected to impact the overall confinement function of the aluminum cladding.

  10. CORROSION OF ALUMINUM CLAD SPENT NUCLEAR FUEL IN THE 70 TON CASK DURING TRANSFER FROM L AREA TO H-CANYON

    SciTech Connect (OSTI)

    Mickalonis, J.

    2014-06-01

    Aluminum-clad spent nuclear fuel will be transported for processing in the 70-ton nuclear fuel element cask from L Basin to H-canyon. During transport these fuels would be expected to experience high temperature aqueous corrosion from the residual L Basin water that will be present in the cask. Cladding corrosion losses during transport were calculated for material test reactor (MTR) and high flux isotope reactors (HFIR) fuels using literature and site information on aqueous corrosion at a range of time/temperature conditions. Calculations of the cladding corrosion loss were based on Arrhenius relationships developed for aluminum alloys typical of cladding material with the primary assumption that an adherent passive film does not form to retard the initial corrosion rate. For MTR fuels a cladding thickness loss of 33 % was found after 1 year in the cask with a maximum temperature of 260 {degrees}C. HFIR fuels showed a thickness loss of only 6% after 1 year at a maximum temperature of 180 {degrees}C. These losses are not expected to impact the overall confinement function of the aluminum cladding.

  11. Nuclear Energy Programs

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Nuclear Energy Programs Solving Nuclear Energy Technical Challenges Our science and technology are making way for new nuclear fuels and reactor materials. Get Expertise David Teter Email Generating breakthroughs in nuclear energy materials Safe and sustainable nuclear energy is a focus of the Laboratory's energy security mission, and our expertise in materials science plays an important role. With collaborators worldwide, Los Alamos is developing technologies for future nuclear reactor designs

  12. Nuclear Fuel Cycle & Vulnerabilities

    SciTech Connect (OSTI)

    Boyer, Brian D.

    2012-06-18

    The objective of safeguards is the timely detection of diversion of significant quantities of nuclear material from peaceful nuclear activities to the manufacture of nuclear weapons or of other nuclear explosive devices or for purposes unknown, and deterrence of such diversion by the risk of early detection. The safeguards system should be designed to provide credible assurances that there has been no diversion of declared nuclear material and no undeclared nuclear material and activities.

  13. Advancing Global Nuclear Security

    Office of Energy Efficiency and Renewable Energy (EERE)

    Today world leaders gathered at The Hague for the Nuclear Security Summit, a meeting to measure progress and take action to secure sensitive nuclear materials.

  14. Nuclear Security Summit

    National Nuclear Security Administration (NNSA)

    Joint Research Centre and the United States Department of Energy's National Nuclear Security Administration regarding the reduction of excess nuclear material http:...

  15. Method for recovery of actinides from actinide-bearing scrap and waste nuclear material using O/sub 2/F/sub 2/

    DOE Patents [OSTI]

    Asprey, L.B.; Eller, P.G.

    1984-09-12

    Method for recovery of actinides from nuclear waste material containing sintered and other oxides thereof and from scrap materials containing the metal actinides using O/sub 2/F/sub 2/ to generate the hexafluorides of the actinides present therein. The fluorinating agent, O/sub 2/F/sub 2/, has been observed to perform the above-described tasks at sufficiently low temperatures that there is virtually no damage to the containment vessels. Moreover, the resulting actinide hexafluorides are not detroyed by high temperature reactions with the walls of the reaction vessel. Dioxygen difluoride is readily prepared, stored and transferred to the place of reaction.

  16. Corrosion of copper as a used nuclear fuel disposal container material: effects of sulfide ions and gamma radiolysis. Report No. 89-211-K

    SciTech Connect (OSTI)

    Lam, K.W.

    1990-01-01

    Review of the corrosion performance of copper as a container material for the disposal of used nuclear fuel. The review determined long-term corrosion data for copper in a saline groundwater-sodium bentonite slurry and derived a rate equation for a diffusion limited corrosion reaction for comparison with the empirical data. The effects of oxygen, salinity, temperatures, sulfide ions and gamma radiation on copper's corrosion rate were examined and the corrosion products identified.

  17. Microsoft PowerPoint - NMMSS Strategy_Analytical Approach for Validating the Accuracy Of Nuclear Material Data_Richard Meehan_M

    National Nuclear Security Administration (NNSA)

    Strategy and Analytical Approach for Validating the Accuracy Of Nuclear Material Data Mitch Hembree NMMSS Richard Meehan NNSA Purpose  NMMSS Provides information and data of significance to the U.S. Government.  Data integrity is of paramount importance.  This presentation provides an overview of NMMSS strategy and analytical approach to data validation. 2 Context Validation and verification of NMMSS data are critical in the ability to provide high quality, accurate and complete

  18. MATERIAL CONTROL ACCOUNTING INMM

    SciTech Connect (OSTI)

    Hasty, T.

    2009-06-14

    Since 1996, the Mining and Chemical Combine (MCC - formerly known as K-26), and the United States Department of Energy (DOE) have been cooperating under the cooperative Nuclear Material Protection, Control and Accounting (MPC&A) Program between the Russian Federation and the U.S. Governments. Since MCC continues to operate a reactor for steam and electricity production for the site and city of Zheleznogorsk which results in production of the weapons grade plutonium, one of the goals of the MPC&A program is to support implementation of an expanded comprehensive nuclear material control and accounting (MC&A) program. To date MCC has completed upgrades identified in the initial gap analysis and documented in the site MC&A Plan and is implementing additional upgrades identified during an update to the gap analysis. The scope of these upgrades includes implementation of MCC organization structure relating to MC&A, establishing material balance area structure for special nuclear materials (SNM) storage and bulk processing areas, and material control functions including SNM portal monitors at target locations. Material accounting function upgrades include enhancements in the conduct of physical inventories, limit of error inventory difference procedure enhancements, implementation of basic computerized accounting system for four SNM storage areas, implementation of measurement equipment for improved accountability reporting, and both new and revised site-level MC&A procedures. This paper will discuss the implementation of MC&A upgrades at MCC based on the requirements established in the comprehensive MC&A plan developed by the Mining and Chemical Combine as part of the MPC&A Program.

  19. Materials and Molecular Research Division. Annual report 1981

    SciTech Connect (OSTI)

    Not Available

    1982-08-01

    Progress is reported in the areas of materials sciences, chemical sciences, nuclear sciences, fossil energy, advanced (laser) isotope separation technology, energy storage, superconducting magnets, and nuclear waste management. Work for others included phase equilibria for coal gasification products and ..beta..-alumina electrolytes for storage batteries. (DLC)

  20. Security and Use Control of Nuclear Explosives and Nuclear Weapons...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    O 452.4C, Security and Use Control of Nuclear Explosives and Nuclear Weapons by LtCol Karl Basham Functional areas: Nuclear Explosives, Nuclear Weapons, Security, Safety, Weapon...

  1. Review of Destructive Assay Methods for Nuclear Materials Characterization from the Three Mile Island (TMI) Fuel Debris

    SciTech Connect (OSTI)

    Carla J. Miller

    2013-09-01

    This report provides a summary of the literature review that was performed and based on previous work performed at the Idaho National Laboratory studying the Three Mile Island 2 (TMI-2) nuclear reactor accident, specifically the melted fuel debris. The purpose of the literature review was to document prior published work that supports the feasibility of the analytical techniques that were developed to provide quantitative results of the make-up of the fuel and reactor component debris located inside and outside the containment. The quantitative analysis provides a technique to perform nuclear fuel accountancy measurements

  2. material removal

    National Nuclear Security Administration (NNSA)

    %2A en Nuclear Material Removal http:nnsa.energy.govaboutusourprogramsdnnm3remove

    Page...

  3. material removal

    National Nuclear Security Administration (NNSA)

    %2A en Nuclear Material Removal http:www.nnsa.energy.govaboutusourprogramsdnnm3remove

    Pag...

  4. Bubble Density Dependent Functionals to Describe Deformation and Stress Equilibrium Evolution for In-Reactor Nuclear Fuel Materials

    SciTech Connect (OSTI)

    Stout, Ray B.

    2008-07-01

    Future designs of nuclear fuels require an increased understanding of fission gas bubble density evolution. Derivations will be provided for a generic Boltzmann bubble density evolution equation, a bubble density deformation field equation, and a Cauchy stress/bubble-pressure equilibrium equation. (author)

  5. An Assessment of the Current Day Impact of Various Materials Associated with the U.S. Nuclear Test Program in the Marshall Island

    SciTech Connect (OSTI)

    Robison, W L; Noshkin, V E; Hamilton, T F; Conrado, C L; Bogen, K T

    2001-05-01

    Different stable elements, and some natural and man-made radionuclides, were used as tracers or associated in other ways with nuclear devices that were detonated at Bikini and Enewetak Atolls as part of the U.S. nuclear testing program from 1946 through 1958. The question has been raised whether any of these materials dispersed by the explosions could be of sufficient concentration in either the marine environment or on the coral islands to be of a health concern to people living, or planning to live, on the atolls. This report addresses that concern. An inventory of the materials involved during the test period was prepared and provided to us by the Office of Defense Programs (DP) of the United States Department of Energy (DOE). The materials that the DOE and the Republic of the Marshall Islands (RMI) ask to be evaluated are--sulfur, arsenic, yttrium, tantalum, gold, rhodium, indium, tungsten, thallium, thorium-230,232 ({sup 230,232}Th), uranium-233,238 ({sup 233,238}U), polonium-210 ({sup 210}Po), curium-232 ({sup 232}Cu), and americium-241 ({sup 241}Am). The stable elements were used primarily as tracers for determining neutron energy and flux, and for other diagnostic purposes in the larger yield, multistage devices. It is reasonable to assume that these materials would be distributed in a similar manner as the fission products subsequent to detonation. A large inventory of fission product and uranium data was available for assessment. Detailed calculations show only a very small fraction of the fission products produced during the entire test series remain at the test site atolls. Consequently, based on the information provided, we conclude that the concentration of these materials in the atoll environment pose no adverse health effects to humans.

  6. Nuclear Technology Programs

    SciTech Connect (OSTI)

    Harmon, J.E.

    1990-10-01

    This document reports on the work done by the Nuclear Technology Programs of the Chemical Technology Division, Argonne National Laboratory, in the period April--September 1988. These programs involve R D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management. The work in applied physical chemistry includes investigations into the processes that control the release and transport of fission products under accident-like conditions, the thermophysical properties of selected materials in environments simulating those of fusion energy systems. In the area of separation science and technology, the bulk of the effort is concerned with developing and implementing processes for the removal and concentration of actinides from waste streams contaminated by transuranic elements. Another effort is concerned with examining the feasibility of substituting low-enriched for high-enriched uranium in the production of fission-product {sup 99}Mo. In the area of waste management, investigations are underway on the performance of materials in projected nuclear repository conditions to provide input to the licensing of the nation's high-level waste repositories.

  7. Water-Stable Zirconium-Based Metal-Organic Framework Material with High-Surface Area and Gas-Storage Capacities

    SciTech Connect (OSTI)

    Gutov, OV; Bury, W; Gomez-Gualdron, DA; Krungleviciute, V; Fairen-Jimenez, D; Mondloch, JE; Sarjeant, AA; Al-Juaid, SS; Snurr, RQ; Hupp, JT; Yildirim, T; Farha, OK

    2014-08-14

    We designed, synthesized, and characterized a new Zr-based metal-organic framework material, NU-1100, with a pore volume of 1.53 ccg(-1) and Brunauer-Emmett-Teller (BET) surface area of 4020 m(2)g(-1); to our knowledge, currently the highest published for Zr-based MOFs. CH4/CO2/H-2 adsorption isotherms were obtained over a broad range of pressures and temperatures and are in excellent agreement with the computational predictions. The total hydrogen adsorption at 65 bar and 77 K is 0.092 gg(-1), which corresponds to 43 gL(-1). The volumetric and gravimetric methane-storage capacities at 65 bar and 298 K are approximately 180 v(STP)/v and 0.27 gg(-1), respectively.

  8. Reference Materials

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Reference Materials (continued) * Generators are required to avoid Las Vegas metropolitan area and Hoover Dam (Section 6.4 of NNSS Waste Acceptance Criteria, available at ...

  9. Spent Fuel Working Group report on inventory and storage of the Department`s spent nuclear fuel and other reactor irradiated nuclear materials and their environmental, safety and health vulnerabilities. Volume 3, Site team reports

    SciTech Connect (OSTI)

    Not Available

    1993-11-01

    A self assessment was conducted of those Hanford facilities that are utilized to store Reactor Irradiated Nuclear Material, (RINM). The objective of the assessment is to identify the Hanford inventories of RINM and the ES & H concerns associated with such storage. The assessment was performed as proscribed by the Project Plan issued by the DOE Spent Fuel Working Group. The Project Plan is the plan of execution intended to complete the Secretary`s request for information relevant to the inventories and vulnerabilities of DOE storage of spent nuclear fuel. The Hanford RINM inventory, the facilities involved and the nature of the fuel stored are summarized. This table succinctly reveals the variety of the Hanford facilities involved, the variety of the types of RINM involved, and the wide range of the quantities of material involved in Hanford`s RINM storage circumstances. ES & H concerns are defined as those circumstances that have the potential, now or in the future, to lead to a criticality event, to a worker radiation exposure event, to an environmental release event, or to public announcements of such circumstances and the sensationalized reporting of the inherent risks.

  10. Research and Development | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    capabilities to detect, identify, and characterize: 1) foreign nuclear weapons programs, 2) illicit diversion of special nuclear materials, and 3) global nuclear detonations. ...

  11. Implementing New Methods of Laser Marking of Items in the Nuclear Material Control and Accountability System at SSC RF-IPPE: An Automated Laser Marking System

    SciTech Connect (OSTI)

    Regoushevsky, V I; Tambovtsev, S D; Dvukhsherstnov, V G; Efimenko, V F; Ilyantsev, A I; Russ III, G P

    2009-05-18

    For over ten years SSC RF-IPPE, together with the US DOE National Laboratories, has been working on implementing automated control and accountability methods for nuclear materials and other items. Initial efforts to use adhesive bar codes or ones printed (painted) onto metal revealed that these methods were inconvenient and lacked durability under operational conditions. For NM disk applications in critical stands, there is the additional requirement that labels not affect the neutron characteristics of the critical assembly. This is particularly true for the many stainless-steel clad disks containing highly enriched uranium (HEU) and plutonium that are used at SSC RF-IPPE for modeling nuclear power reactors. In search of an alternate method for labeling these disks, we tested several technological options, including laser marking and two-dimensional codes. As a result, the method of laser coloring was chosen in combination with Data Matrix ECC200 symbology. To implement laser marking procedures for the HEU disks and meet all the nuclear material (NM) handling standards and rules, IPPE staff, with U.S. technical and financial support, implemented an automated laser marking system; there are also specially developed procedures for NM movements during laser marking. For the laser marking station, a Zenith 10F system by Telesis Technologies (10 watt Ytterbium Fiber Laser and Merlin software) is used. The presentation includes a flowchart for the automated system and a list of specially developed procedures with comments. Among other things, approaches are discussed for human-factor considerations. To date, markings have been applied to numerous steel-clad HEU disks, and the work continues. In the future this method is expected to be applied to other MC&A items.

  12. Plutonium focus area

    SciTech Connect (OSTI)

    1996-08-01

    To ensure research and development programs focus on the most pressing environmental restoration and waste management problems at the U.S. Department of Energy (DOE), the Assistant Secretary for the Office of Environmental Management (EM) established a working group in August 1993 to implement a new approach to research and technology development. As part of this new approach, EM developed a management structure and principles that led to the creation of specific Focus Areas. These organizations were designed to focus the scientific and technical talent throughout DOE and the national scientific community on the major environmental restoration and waste management problems facing DOE. The Focus Area approach provides the framework for intersite cooperation and leveraging of resources on common problems. After the original establishment of five major Focus Areas within the Office of Technology Development (EM-50, now called the Office of Science and Technology), the Nuclear Materials Stabilization Task Group (EM-66) followed the structure already in place in EM-50 and chartered the Plutonium Focus Area (PFA). The following information outlines the scope and mission of the EM, EM-60, and EM-66 organizations as related to the PFA organizational structure.

  13. Newsletters | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    About Us / Our Programs / Defense Nuclear Security / Nuclear Materials Management & Safeguards System / NMMSS Information, Reports & Forms / Newsletters Newsletters U.S. Department of Energy / U.S. Nuclear Regulatory Commission Nuclear Materials Management & Safeguards System Newsletters NMMSS is sponsored by the National Nuclear Security Administration's (NNSA) Office of Materials Integration within the U.S. Department of Energy and the U.S. Nuclear Regulatory Commission Attachment

  14. Materials Videos

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Materials Videos Materials

  15. Sandia Teaches Nuclear Safety Course

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ... and policy makers from 36 countries who recently completyed the three-week international training course on the physical protection of nuclear material and nuclear facilities. ...

  16. Safer nuclear power

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Safer nuclear power 1663 Los Alamos science and technology magazine Latest Issue:October 2015 past issues All Issues » submit Safer nuclear power Experiments at Los Alamos reveal that alternative fuel rod cladding materials can make nuclear power plants dramatically less likely to suffer a Fukushima-type explosion in the event of a nuclear accident March 25, 2013 Safer nuclear power Nuclear generating station Los Alamos scientists, in collaboration with scientists from the Idaho and Oak Ridge

  17. Tanks Focus Area annual report FY2000

    SciTech Connect (OSTI)

    2000-12-01

    The U.S. Department of Energy (DOE) continues to face a major radioactive waste tank remediation effort with tanks containing hazardous and radioactive waste resulting from the production of nuclear materials. With some 90 million gallons of waste in the form of solid, sludge, liquid, and gas stored in 287 tanks across the DOE complex, containing approximately 650 million curies, radioactive waste storage tank remediation is the nation's highest cleanup priority. Differing waste types and unique technical issues require specialized science and technology to achieve tank cleanup in an environmentally acceptable manner. Some of the waste has been stored for over 50 years in tanks that have exceeded their design lives. The challenge is to characterize and maintain these contents in a safe condition and continue to remediate and close each tank to minimize the risks of waste migration and exposure to workers, the public, and the environment. In 1994, the DOE's Office of Environmental Management (EM) created a group of integrated, multiorganizational teams focusing on specific areas of the EM cleanup mission. These teams have evolved into five focus areas managed within EM's Office of Science and Technology (OST): Tanks Focus Area (TFA); Deactivation and Decommissioning Focus Area; Nuclear Materials Focus Area; Subsurface Contaminants Focus Area; and Transuranic and Mixed Waste Focus Area.

  18. Fate and transport processes controlling the migration of hazardous and radioactive materials from the Area 5 Radioactive Waste Management Site (RWMS)

    SciTech Connect (OSTI)

    Estrella, R.

    1994-10-01

    Desert vadose zones have been considered as suitable environments for the safe and long-term isolation of hazardous wastes. Low precipitation, high evapotranspiration and thick unsaturated alluvial deposits commonly found in deserts make them attractive as waste disposal sites. The fate and transport of any contaminant in the subsurface is ultimately determined by the operating retention and transformation processes in the system and the end result of the interactions among them. Retention (sorption) and transformation are the two major processes that affect the amount of a contaminant present and available for transport. Retention processes do not affect the total amount of a contaminant in the soil system, but rather decrease or eliminate the amount available for transport at a given point in time. Sorption reactions retard the contaminant migration. Permanent binding of solute by the sorbent is also possible. These processes and their interactions are controlled by the nature of the hazardous waste, the properties of the porous media and the geochemical and environmental conditions (temperature, moisture and vegetation). The present study summarizes the available data and investigates the fate and transport processes that govern the migration of contaminants from the Radioactive Waste Management Site (RWMS) in Area 5 of the Nevada Test Site (NTS). While the site is currently used only for low-level radioactive waste disposal, past practices have included burial of material now considered hazardous. Fundamentals of chemical and biological transformation processes are discussed subsequently, followed by a discussion of relevant results.

  19. Nuclear Physics & Modeling, AFC R&D Nuclear Physics Working Group...

    Office of Scientific and Technical Information (OSTI)

    (LANL) Sponsoring Org: DOELANL Country of Publication: United States Language: English Subject: Atomic and Nuclear Physics; Nuclear Fuel Cycle & Fuel Materials(11); Nuclear...

  20. Final Report: Part 1. In-Place Filter Testing Instrument for Nuclear Material Containers. Part 2. Canister Filter Test Standards for Aerosol Capture Rates.

    SciTech Connect (OSTI)

    Brown, Austin Douglas; Runnels, Joel T.; Moore, Murray E.; Reeves, Kirk Patrick

    2014-11-02

    A portable instrument has been developed to assess the functionality of filter sand o-rings on nuclear material storage canisters, without requiring removal of the canister lid. Additionally, a set of fifteen filter standards were procured for verifying aerosol leakage and pressure drop measurements in the Los Alamos Filter Test System. The US Department of Energy uses several thousand canisters for storing nuclear material in different chemical and physical forms. Specialized filters are installed into canister lids to allow gases to escape, and to maintain an internal ambient pressure while containing radioactive contaminants. Diagnosing the condition of container filters and canister integrity is important to ensure worker and public safety and for determining the handling requirements of legacy apparatus. This report describes the In-Place-Filter-Tester, the Instrument Development Plan and the Instrument Operating Method that were developed at the Los Alamos National Laboratory to determine the as found condition of unopened storage canisters. The Instrument Operating Method provides instructions for future evaluations of as-found canisters packaged with nuclear material. Customized stainless steel canister interfaces were developed for pressure-port access and to apply a suction clamping force for the interface. These are compatible with selected Hagan-style and SAVY-4000 storage canisters that were purchased from NFT (Nuclear Filter Technology, Golden, CO). Two instruments were developed for this effort: an initial Los Alamos POC (Proof-of-Concept) unit and the final Los Alamos IPFT system. The Los Alamos POC was used to create the Instrument Development Plan: (1) to determine the air flow and pressure characteristics associated with canister filter clogging, and (2) to test simulated configurations that mimicked canister leakage paths. The canister leakage scenarios included quantifying: (A) air leakage due to foreign material (i.e. dust and hair) fouling of o-rings, (B) leakage through simulated cracks in o-rings, and (C) air leakage due to inadequately tightened canister lids. The Los Alamos POC instrument determined pertinent air flow and pressure quantities, and this knowledge was used to specify a customized Isaac (Z axis, Salt Lake City, UT) leak test module. The final Los Alamos IPFT (incorporating the Isaac leak test module) was used to repeat the tests in the Instrument Development Plan (with simulated filter clogging tests and canister leak pathway tests). The Los Alamos IPFT instrument is capable of determining filter clogging and leak rate conditions, without requiring removal of the container lid. The IPFT measures pressure decay rate from 1.7E-03 in WC/sec to 1.7E-01 in WC/sec. On the same unit scale, helium leak testing of canisters has a range from 5.7E-07 in WC/sec to 1.9E-03 in WC/sec. For a 5-quart storage canister, the IPFT measures equivalent leak flow rates from 0.03 to 3.0 cc/sec. The IPFT does not provide the same sensitivity as helium leak testing, but is able to gauge the assembled condition of as-found and in-situ canisters.

  1. NEW MATERIALS DEVELOPED TO MEET REGULATORY AND TECHNICAL REQUIREMENTS ASSOCIATED WITH IN-SITU DECOMMISSIONING OF NUCLEAR REACTORS AND ASSOCIATED FACILITIES

    SciTech Connect (OSTI)

    Blankenship, J.; Langton, C.; Musall, J.; Griffin, W.

    2012-01-18

    For the 2010 ANS Embedded Topical Meeting on Decommissioning, Decontamination and Reutilization and Technology, Savannah River National Laboratory's Mike Serrato reported initial information on the newly developed specialty grout materials necessary to satisfy all requirements associated with in-situ decommissioning of P-Reactor and R-Reactor at the U.S. Department of Energy's Savannah River Site. Since that report, both projects have been successfully completed and extensive test data on both fresh properties and cured properties has been gathered and analyzed for a total of almost 191,150 m{sup 3} (250,000 yd{sup 3}) of new materials placed. The focus of this paper is to describe the (1) special grout mix for filling the P-Reactor vessel (RV) and (2) the new flowable structural fill materials used to fill the below grade portions of the facilities. With a wealth of data now in hand, this paper also captures the test results and reports on the performance of these new materials. Both reactors were constructed and entered service in the early 1950s, producing weapons grade materials for the nation's defense nuclear program. R-Reactor was shut down in 1964 and the P-Reactor in 1991. In-situ decommissioning (ISD) was selected for both facilities and performed as Comprehensive Environmental Response, Compensations and Liability Act actions (an early action for P-Reactor and a removal action for R-Reactor), beginning in October 2009. The U.S. Department of Energy concept for ISD is to physically stabilize and isolate intact, structurally robust facilities that are no longer needed for their original purpose of producing (reactor facilities), processing (isotope separation facilities), or storing radioactive materials. Funding for accelerated decommissioning was provided under the American Recovery and Reinvestment Act. Decommissioning of both facilities was completed in September 2011. ISD objectives for these CERCLA actions included: (1) Prevent industrial worker exposure to radioactive or hazardous contamination exceeding Principal Threat Source Material levels; (2) Minimize human and ecological exposure to unacceptable risk associated with radiological and hazardous constituents that are or may be present; (3) Prevent to the extent practicable the migration of radioactive or hazardous contaminants from the closed facility to the groundwater so that concentrations in groundwater do not exceed regulatory standards; (4) Eliminate or control all routes of human exposure to radiological and chemical contamination; and (5) Prevent animal intruder exposure to radioactive and hazardous contamination.

  2. Corrective Action Decision Document for Corrective Action Unit 168: Area 25 and 26 Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada, Rev. No.: 2 with Errata Sheet

    SciTech Connect (OSTI)

    Wickline, Alfred

    2006-12-01

    This Corrective Action Decision Document has been prepared for Corrective Action Unit (CAU) 168: Area 25 and 26, Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada. The purpose of this Corrective Action Decision Document is to identify and provide a rationale for the selection of a recommended corrective action alternative for each corrective action site (CAS) within CAU 168. The corrective action investigation (CAI) was conducted in accordance with the ''Corrective Action Investigation Plan for Corrective Action Unit 168: Area 25 and 26, Contaminated Materials and Waste Dumps, Nevada Test Site, Nevada'', as developed under the ''Federal Facility Agreement and Consent Order'' (1996). Corrective Action Unit 168 is located in Areas 25 and 26 of the Nevada Test Site, Nevada and is comprised of the following 12 CASs: CAS 25-16-01, Construction Waste Pile; CAS 25-16-03, MX Construction Landfill; CAS 25-19-02, Waste Disposal Site; CAS 25-23-02, Radioactive Storage RR Cars; CAS 25-23-13, ETL - Lab Radioactive Contamination; CAS 25-23-18, Radioactive Material Storage; CAS 25-34-01, NRDS Contaminated Bunker; CAS 25-34-02, NRDS Contaminated Bunker; CAS 25-99-16, USW G3; CAS 26-08-01, Waste Dump/Burn Pit; CAS 26-17-01, Pluto Waste Holding Area; and CAS 26-19-02, Contaminated Waste Dump No.2. Analytes detected during the CAI were evaluated against preliminary action levels (PALs) to determine contaminants of concern (COCs) for CASs within CAU 168. Radiological measurements of railroad cars and test equipment were compared to unrestricted (free) release criteria. Assessment of the data generated from the CAI activities revealed the following: (1) Corrective Action Site 25-16-01 contains hydrocarbon-contaminated soil at concentrations exceeding the PAL. The contamination is at discrete locations associated with asphalt debris. (2) No COCs were identified at CAS 25-16-03. Buried construction waste is present in at least two disposal cells contained within the landfill boundaries. (3) No COCs were identified at CAS 25-19-02. (4) Radiological surveys at CAS 25-23-02 identified 13 railroad cars that exceeded the NV/YMP Radiological Control Manual limits for free release. Six railroad cars were below these limits and therefore met the free-release criteria. (5) An In-Situ Object Counting System survey taken at CAS 25-23-02 identified two railroad cars possibly containing fuel fragments; both exceeded the NV/YMP Radiological Control Manual free release criteria. (6) Corrective Action Site 25-23-18 contains total petroleum hydrocarbons-diesel-range organics, Aroclor-1260, uranium-234, uranium-235, strontium-90, and cesium-137 that exceed PALs. (7) Radiological surveys at CAS 25-34-01 indicate that there were no total contamination readings that exceeded the NV/YMP Radiological Control Manual limits for free release. (8) Radiological surveys at CAS 25-34-02 indicate that there were no total contamination readings that exceeded the NV/YMP Radiological Control Manual limits for free release. (9) Radiological surveys at CAS 25-23-13 identified six pieces of equipment that exceed the NV/YMP Radiological Control Manual limits for free release. (10) Corrective Action Site 25-99-16 was not investigated. A review of historical documentation and current site conditions showed that no further characterization was required to select the appropriate corrective action. (11) Corrective Action Site 26-08-01 contains hydrocarbon-contaminated soil at concentrations exceeding the PAL. The contamination is at discrete locations associated with asphalt debris. (12) Corrective Action Site 26-17-01 contains total petroleum hydrocarbons-diesel-range organics and Aroclor-1260 exceeding the PALs. (13) Radiological surveys at CAS 26-19-02 identified metallic debris that exceeded the NV/YMP Radiological Control Manual limits for free release. Concentrations of radiological or chemical constituents in soil did not exceed PALs.

  3. DEVELOPMENT OF PLASTICITY MODEL USING NON ASSOCIATED FLOW RULE FOR HCP MATERIALS INCLUDING ZIRCONIUM FOR NUCLEAR APPLICATIONS

    SciTech Connect (OSTI)

    Michael V. Glazoff; Jeong-Whan Yoon

    2013-08-01

    In this report (prepared in collaboration with Prof. Jeong Whan Yoon, Deakin University, Melbourne, Australia) a research effort was made to develop a non associated flow rule for zirconium. Since Zr is a hexagonally close packed (hcp) material, it is impossible to describe its plastic response under arbitrary loading conditions with any associated flow rule (e.g. von Mises). As a result of strong tension compression asymmetry of the yield stress and anisotropy, zirconium displays plastic behavior that requires a more sophisticated approach. Consequently, a new general asymmetric yield function has been developed which accommodates mathematically the four directional anisotropies along 0 degrees, 45 degrees, 90 degrees, and biaxial, under tension and compression. Stress anisotropy has been completely decoupled from the r value by using non associated flow plasticity, where yield function and plastic potential have been treated separately to take care of stress and r value directionalities, respectively. This theoretical development has been verified using Zr alloys at room temperature as an example as these materials have very strong SD (Strength Differential) effect. The proposed yield function reasonably well models the evolution of yield surfaces for a zirconium clock rolled plate during in plane and through thickness compression. It has been found that this function can predict both tension and compression asymmetry mathematically without any numerical tolerance and shows the significant improvement compared to any reported functions. Finally, in the end of the report, a program of further research is outlined aimed at constructing tensorial relationships for the temperature and fluence dependent creep surfaces for Zr, Zircaloy 2, and Zircaloy 4.

  4. Meeting Materials

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    BER Meeting Materials Meeting Materials Here you will find various items to be used before and during the requirements review. The following documents are included: Case study worksheet to be filled in by meeting participants Sample of a completed case study from a Nuclear Physics requirements workshop held in 2011 A graph of NERSC and BER usage as a function of time A powerpoint template you can use at the requirements review Downloads RequirementsWorkshopCaseStudyTemplate.doc | Word document

  5. Meeting Materials

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    HEP Meeting Materials Meeting Materials Here you will find various items to be used before and during the requirements review. The following documents are included: Case study worksheet to be filled in by meeting participants Sample of a completed case study from a Nuclear Physics requirements workshop held in 2011 A graph of NERSC and HEP usage as a function of time A powerpoint template you can use at the requirements review Downloads CaseStudyTemplate.docx | unknown Case Study Worksheet -

  6. Materials Degradation and Detection (MD2): Deep Dive Final Report

    SciTech Connect (OSTI)

    McCloy, John S.; Montgomery, Robert O.; Ramuhalli, Pradeep; Meyer, Ryan M.; Hu, Shenyang Y.; Li, Yulan; Henager, Charles H.; Johnson, Bradley R.

    2013-02-01

    An effort is underway at Pacific Northwest National Laboratory (PNNL) to develop a fundamental and general framework to foster the science and technology needed to support real-time monitoring of early degradation in materials used in the production of nuclear power. The development of such a capability would represent a timely solution to the mounting issues operators face with materials degradation in nuclear power plants. The envisioned framework consists of three primary and interconnected “thrust” areas including 1) microstructural science, 2) behavior assessment, and 3) monitoring and predictive capabilities. A brief state-of-the-art assessment for each of these core technology areas is discussed in the paper.

  7. NUCLEAR MATERIALTRANSACTION REPORT | Department of Energy

    Office of Environmental Management (EM)

    NUCLEAR MATERIALTRANSACTION REPORT NUCLEAR MATERIALTRANSACTION REPORT Form used to support nuclear materials accountability and control. PDF icon NUCLEAR MATERIALTRANSACTION REPORT More Documents & Publications DOE/NRC F 742 DOE F 749 DOE F 5635.9

  8. Neutron and Nuclear Science News

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    News Recent news and events related to neutron and nuclear science at LANSCE. Neutron and Nuclear Science News Nuclear and Materials Science Research at LANSCE Nuclear science observations and opportunities at the Los Alamos Neutron Science Center Links Neutron and Nuclear Science News Media Links Profiles Events at LANSCE LAPIS (LANSCE Proposal Intake System

  9. WIPP Nuclear Facilities Transparency

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    the safety, security, and legitimate management of nuclear materials." Other Links Yucca Mountain Test Data Carlsbad Environmental Monitoring and Research Center Dimitrovograd...

  10. Improved Technology To Prevent Nuclear Proliferation And Counter Nuclear Terrorism

    SciTech Connect (OSTI)

    Richardson, J; Yuldashev, B; Labov, S; Knapp, R

    2006-06-12

    As the world moves into the 21st century, the possibility of greater reliance on nuclear energy will impose additional technical requirements to prevent proliferation. In addition to proliferation resistant reactors, a careful examination of the various possible fuel cycles from cradle to grave will provide additional technical and nonproliferation challenges in the areas of conversion, enrichment, transportation, recycling and waste disposal. Radiation detection technology and information management have a prominent role in any future global regime for nonproliferation. As nuclear energy and hence nuclear materials become an increasingly global phenomenon, using local technologies and capabilities facilitate incorporation of enhanced monitoring and detection on the regional level. Radiation detection technologies are an important tool in the prevention of proliferation and countering radiological/nuclear terrorism. A variety of new developments have enabled enhanced performance in terms of energy resolution, spatial resolution, passive detection, predictive modeling and simulation, active interrogation, and ease of operation and deployment in the field. For example, various gamma ray imaging approaches are being explored to combine spatial resolution with background suppression in order to enhance sensitivity many-fold at reasonable standoff distances and acquisition times. New materials and approaches are being developed in order to provide adequate energy resolution in field use without the necessity for liquid nitrogen. Different detection algorithms enable fissile materials to be distinguished from other radioisotopes.

  11. NUCLEAR REACTOR

    DOE Patents [OSTI]

    Grebe, J.J.

    1959-07-14

    High temperature reactors which are uniquely adapted to serve as the heat source for nuclear pcwered rockets are described. The reactor is comprised essentially of an outer tubular heat resistant casing which provides the main coolant passageway to and away from the reactor core within the casing and in which the working fluid is preferably hydrogen or helium gas which is permitted to vaporize from a liquid storage tank. The reactor core has a generally spherical shape formed entirely of an active material comprised of fissile material and a moderator material which serves as a diluent. The active material is fabricated as a gas permeable porous material and is interlaced in a random manner with very small inter-connecting bores or capillary tubes through which the coolant gas may flow. The entire reactor is divided into successive sections along the direction of the temperature gradient or coolant flow, each section utilizing materials of construction which are most advantageous from a nuclear standpoint and which at the same time can withstand the operating temperature of that particular zone. This design results in a nuclear reactor characterized simultaneously by a minimum critiral size and mass and by the ability to heat a working fluid to an extremely high temperature.

  12. National Nuclear Security Administration ENERGY U.S. DEPARTMENT...

    National Nuclear Security Administration (NNSA)

    Concepts and Approaches 3. International Nuclear Safeguards Engagement 4. Technology ... and evaluating advanced methods to safeguard nuclear material and facilities. ...

  13. An interactive ontology-driven information system for simulating background radiation and generating scenarios for testing special nuclear materials detection algorithms

    SciTech Connect (OSTI)

    Sorokine, Alexandre; Schlicher, Bob G; Ward, Richard C; Wright, Michael C; Kruse, Kara L

    2015-01-01

    This paper describes an original approach to generating scenarios for the purpose of testing the algorithms used to detect special nuclear materials (SNM) that incorporates the use of ontologies. Separating the signal of SNM from the background requires sophisticated algorithms. To assist in developing such algorithms, there is a need for scenarios that capture a very wide range of variables affecting the detection process, depending on the type of detector being used. To provide such a cpability, we developed an ontology-driven information system (ODIS) for generating scenarios that can be used in creating scenarios for testing of algorithms for SNM detection. The ontology-driven scenario generator (ODSG) is an ODIS based on information supplied by subject matter experts and other documentation. The details of the creation of the ontology, the development of the ontology-driven information system, and the design of the web user interface (UI) are presented along with specific examples of scenarios generated using the ODSG. We demonstrate that the paradigm behind the ODSG is capable of addressing the problem of semantic complexity at both the user and developer levels. Compared to traditional approaches, an ODIS provides benefits such as faithful representation of the users' domain conceptualization, simplified management of very large and semantically diverse datasets, and the ability to handle frequent changes to the application and the UI. The approach makes possible the generation of a much larger number of specific scenarios based on limited user-supplied information

  14. Environmental consequences of postulate plutonium releases from Atomics International's Nuclear Materials Development Facility (NMDF), Santa Susana, California, as a result of severe natural phenomena

    SciTech Connect (OSTI)

    Jamison, J.D.; Watson, E.C.

    1982-02-01

    Potential environmental consequences in terms of radiation dose to people are presented for postulated plutonium releases caused by severe natural phenomena at the Atomics International's Nuclear Materials Development Facility (NMDF), in the Santa Susana site, California. The severe natural phenomena considered are earthquakes, tornadoes, and high straight-line winds. Plutonium deposition values are given for significant locations around the site. All important potential exposure pathways are examined. The most likely 50-year committed dose equivalents are given for the maximum-exposed individual and the population within a 50-mile radius of the plant. The maximum plutonium deposition values likely to occur offsite are also given. The most likely calculated 50-year collective committed dose equivalents are all much lower than the collective dose equivalent expected from 50 years of exposure to natural background radiation and medical x-rays. The most likely maximum residual plutonium contamination estimated to be deposited offsite following the earthquake, and the 150-mph and 170-mph tornadoes are above the Environmental Protection Agency's (EPA) proposed guideline for plutonium in the general environment of 0.2 ..mu..Ci/m/sup 2/. The deposition values following the 110-mph and the 130-mph tornadoes are below the EPA proposed guideline.

  15. Department of Energy Issues Requests for Applications for Nuclear...

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    Chemistry, Health Physics, Nuclear Materials Science, Radiochemistry, Applied Nuclear Physics, and Nuclear Policy at universities and colleges located in the U.S....

  16. Nuclear Material Control and Accountability

    Broader source: Directives, Delegations, and Requirements [Office of Management (MA)]

    2012-11-19

    These changes are intended to correct typographical and pagination errors, delete a canceled reference and clarify the intent of four metrics in Attachment 3.

  17. Grout Isolation and Stabilization of Structures and Materials within Nuclear Facilities at the U.S. Department of Energy, Hanford Site, Summary - 12309

    SciTech Connect (OSTI)

    Phillips, S.J.; Phillips, M.; Etheridge, D.; Chojnacki, D.W.; Herzog, C.B.; Matosich, B.J.; Steffen, J.M.; Sterling, R.T.; Flaucher, R.H.; Lloyd, E.R.

    2012-07-01

    Per regulatory agreement and facility closure design, U.S. Department of Energy Hanford Site nuclear fuel cycle structures and materials require in situ isolation in perpetuity and/or interim physicochemical stabilization as a part of final disposal or interim waste removal, respectively. To this end, grout materials are being used to encase facilities structures or are being incorporated within structures containing hazardous and radioactive contaminants. Facilities where grout materials have been recently used for isolation and stabilization include: (1) spent fuel separations, (2) uranium trioxide calcining, (3) reactor fuel storage basin, (4) reactor fuel cooling basin transport rail tanker cars and casks, (5) cold vacuum drying and reactor fuel load-out, and (6) plutonium fuel metal finishing. Grout components primarily include: (1) portland cement, (2) fly ash, (3) aggregate, and (4) chemical admixtures. Mix designs for these typically include aggregate and non aggregate slurries and bulk powders. Placement equipment includes: (1) concrete piston line pump or boom pump truck for grout slurry, (2) progressive cavity and shearing vortex pump systems, and (3) extendable boom fork lift for bulk powder dry grout mix. Grout slurries placed within the interior of facilities were typically conveyed utilizing large diameter slick line and the equivalent diameter flexible high pressure concrete conveyance hose. Other facilities requirements dictated use of much smaller diameter flexible grout conveyance hose. Placement required direct operator location within facilities structures in most cases, whereas due to radiological dose concerns, placement has also been completed remotely with significant standoff distances. Grout performance during placement and subsequent to placement often required unique design. For example, grout placed in fuel basin structures to serve as interim stabilization materials required sufficient bearing i.e., unconfined compressive strength, to sustain heavy equipment yet, low breakout force to permit efficient removal by track hoe bucket or equivalent construction equipment. Further, flow of slurries through small orifice geometries of moderate head pressures was another typical design requirement. Phase separation of less than 1 percent was a typical design requirement for slurries. On the order of 30,000 cubic meters of cementitious grout have recently been placed in the above noted U.S. Department of Energy Hanford Site facilities or structures. Each has presented a unique challenge in mix design, equipment, grout injection or placement, and ultimate facility or structure performance. Unconfined compressive and shear strength, flow, density, mass attenuation coefficient, phase separation, air content, wash-out, parameters and others, unique to each facility or structure, dictate the grout mix design for each. Each mix design was tested under laboratory and scaled field conditions as a precursor to field deployment. Further, after injection or placement of each grout formulation, the material was field inspected either by standard laboratory testing protocols, direct physical evaluation, or both. (authors)

  18. Coated ceramic breeder materials

    DOE Patents [OSTI]

    Tam, Shiu-Wing; Johnson, Carl E.

    1987-01-01

    A breeder material for use in a breeder blanket of a nuclear reactor is disclosed. The breeder material comprises a core material of lithium containing ceramic particles which has been coated with a neutron multiplier such as Be or BeO, which coating has a higher thermal conductivity than the core material.

  19. Energy Frontier Research Center Center for Materials Science...

    Office of Scientific and Technical Information (OSTI)

    for Materials Science of Nuclear Fuels Citation Details In-Document Search Title: Energy Frontier Research Center Center for Materials Science of Nuclear Fuels Scientific ...

  20. Follow-up Inspection on Material Control and Accountability at...

    Energy Savers [EERE]

    specified directives on Material Control and Accountability (MC&A) when maintaining certain nuclear materials in support of the Nation's nuclear weapons stockpile program. ...

  1. Office of Material Consolidation & Civilian Sites | National...

    National Nuclear Security Administration (NNSA)

    People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy ... Federation to enhance the security of proliferation-attractive nuclear material by ...

  2. Material Protection, Control, and Accounting Program | National...

    National Nuclear Security Administration (NNSA)

    in preventing nuclear terrorism by working cooperatively with international partners to secure and eliminate potentially vulnerable nuclear weapons and weapons-usable material. ...

  3. Evaluation of the geologic relations and seismotectonic stability of the Yucca Mountain area, Nevada Nuclear Waste Site Investigation (NNWSI); Final report, January 1, 1987--June 30, 1988: Volume 1

    SciTech Connect (OSTI)

    1988-10-01

    This report provides a summary of progress for the project ``Evaluation of the Geologic Relations and Seismotectonic Stability of the Yucca Mountain Area, Nevada Nuclear Waste Site Investigation (NNWSI)`` for the eighteen month period of January 1, 1987 to June 10, 1988. This final report was preceded by the final report for the initial six month period, July 1, 1986 to December 31, 1986 (submitted on January 25, 1987, and revised in June 1987.) Quaternary Tectonics, Geochemical, Mineral Deposits, Vulcanic Geology, Seismology, Tectonics, Neotectonics, Remote Sensing, Geotechnical Assessments, Geotechnical Rock Mass Assessments, Basinal Studies, and Strong Ground Motion.

  4. Materials | Argonne National Laboratory

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Materials Innovating tomorrow's materials today New high-tech materials are the key to breakthroughs in biology, the environment, nuclear energy, transportation and national security. Argonne continues to make revolutionary advances in the science of materials discovery and synthesis, and is designing new materials with advantageous properties - one atom at a time. Examples of these include Argonne's patented technologies for nanoparticle applications, heat transfer and materials for advanced

  5. Combinational pixel-by-pixel and object-level classifying, segmenting, and agglomerating in performing quantitative image analysis that distinguishes between healthy non-cancerous and cancerous cell nuclei and delineates nuclear, cytoplasm, and stromal material objects from stained biological tissue materials

    DOE Patents [OSTI]

    Boucheron, Laura E

    2013-07-16

    Quantitative object and spatial arrangement-level analysis of tissue are detailed using expert (pathologist) input to guide the classification process. A two-step method is disclosed for imaging tissue, by classifying one or more biological materials, e.g. nuclei, cytoplasm, and stroma, in the tissue into one or more identified classes on a pixel-by-pixel basis, and segmenting the identified classes to agglomerate one or more sets of identified pixels into segmented regions. Typically, the one or more biological materials comprises nuclear material, cytoplasm material, and stromal material. The method further allows a user to markup the image subsequent to the classification to re-classify said materials. The markup is performed via a graphic user interface to edit designated regions in the image.

  6. Action Codes Table | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    NNSA Blog Home About Us Our Programs Defense Nuclear Security Nuclear Materials Management & Safeguards System NMMSS Information, Reports & Forms Code Tables Action...

  7. Research and Development | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    NNSA reduces the threat to national security posed by nuclear weapons proliferation and possible detonation or the illicit trafficking of nuclear materials through the long-term...

  8. FY 2014 Consolidated Innovative Nuclear Research FOA

    Broader source: Energy.gov [DOE]

    This Funding Opportunity Announcement (FOA) addresses the competitive portion of NE’s R&D portfolio as executed through the Nuclear Energy University Programs (NEUP) and Nuclear Energy Enabling Technologies Crosscutting Technology Development (NEET CTD). NEUP utilizes up to 20 percent of funds appropriated to NE’s R&D program for university-based infrastructure support and R&D in key NE program-related areas: Fuel Cycle Research and Development (FCR&D), Reactor Concepts Research, Development and Demonstration (RCRD&D), and Nuclear Energy Advanced Modeling and Simulation (NEAMS). NEET CTD supports national laboratory, university and industry led crosscutting research in the areas of reactor materials, advanced sensors and instrumentation, and advanced methods for manufacturing.

  9. Innovations in Nuclear Infrastructure and Education

    SciTech Connect (OSTI)

    John Bernard

    2010-12-13

    The decision to implement the Innovation in Nuclear Infrastructure and Engineering Program (INIE) was an important first step towards ensuring that the United States preserves its worldwide leadership role in the field of nuclear science and engineering. Prior to INIE, university nuclear science and engineering programs were waning, undergraduate student enrollment was down, university research reactors were being shut down, while others faced the real possibility of closure. For too long, cutting edge research in the areas of nuclear medicine, neutron scattering, radiochemistry, and advanced materials was undervalued and therefore underfunded. The INIE program corrected this lapse in focus and direction and started the process of drawing a new blueprint with positive goals and objectives that supports existing as well the next generation of educators, students and researchers.

  10. Nuclear Nonproliferation

    SciTech Connect (OSTI)

    Atkins-Duffin, C E

    2008-12-10

    With an explosion equivalent of about 20kT of TNT, the Trinity test was the first demonstration of a nuclear weapon. Conducted on July 16, 1945 in Alamogordo, NM this site is now a Registered National Historic Landmark. The concept and applicability of nuclear power was demonstrated on December 20, 1951 with the Experimental Breeder Reactor Number One (EBR-1) lit four light bulbs. This reactor is now a Registered National Historic Landmark, located near Arco, ID. From that moment forward it had been clearly demonstrated that nuclear energy has both peaceful and military applications and that the civilian and military fuel cycles can overlap. For the more than fifty years since the Atoms for Peace program, a key objective of nuclear policy has been to enable the wider peaceful use of nuclear energy while preventing the spread of nuclear weapons. Volumes have been written on the impact of these two actions on the world by advocates and critics; pundits and practioners; politicians and technologists. The nations of the world have woven together a delicate balance of treaties, agreements, frameworks and handshakes that are representative of the timeframe in which they were constructed and how they have evolved in time. Collectively these vehicles attempt to keep political will, nuclear materials and technology in check. This paper captures only the briefest abstract of the more significant aspects on the Nonproliferation Regime. Of particular relevance to this discussion is the special nonproliferation sensitivity associated with the uranium isotope separation and spent fuel reprocessing aspects of the nuclear fuel cycle.

  11. The Center for Material Science of Nuclear Fuel (A "Life at the Frontiers of Energy Research" contest entry from the 2011 Energy Frontier Research Centers (EFRCs) Summit and Forum)

    ScienceCinema (OSTI)

    Allen, Todd (Director, Center for Material Science of Nuclear Fuel); CMSNF Staff

    2011-11-02

    'The Center for Material Science of Nuclear Fuel (CMSNF)' was submitted by the CMSNF to the 'Life at the Frontiers of Energy Research' video contest at the 2011 Science for Our Nation's Energy Future: Energy Frontier Research Centers (EFRCs) Summit and Forum. Twenty-six EFRCs created short videos to highlight their mission and their work. CMSNF, an EFRC directed by Todd Allen at the Idaho National Laboratory is a partnership of scientists from six institutions: INL (lead), Colorado School of Mines, University of Florida, Florida State University, Oak Ridge National Laboratory, and the University of Wisconsin at Madison. The Office of Basic Energy Sciences in the U.S. Department of Energy's Office of Science established the 46 Energy Frontier Research Centers (EFRCs) in 2009. These collaboratively-organized centers conduct fundamental research focused on 'grand challenges' and use-inspired 'basic research needs' recently identified in major strategic planning efforts by the scientific community. The overall purpose is to accelerate scientific progress toward meeting the nation's critical energy challenges. The mission of the Center for Materials Science of Nuclear Fuels is 'to achieve a first-principles based understanding of the effect of irradiation-induced defects and microstructures on thermal transport in oxide nuclear fuels.' Research topics are: phonons, thermal conductivity, nuclear, extreme environment, radiation effects, defects, and matter by design.

  12. 2004 research briefs :Materials and Process Sciences Center.

    SciTech Connect (OSTI)

    Cieslak, Michael J.

    2004-01-01

    This report is the latest in a continuing series that highlights the recent technical accomplishments associated with the work being performed within the Materials and Process Sciences Center. Our research and development activities primarily address the materials-engineering needs of Sandia's Nuclear-Weapons (NW) program. In addition, we have significant efforts that support programs managed by the other laboratory business units. Our wide range of activities occurs within six thematic areas: Materials Aging and Reliability, Scientifically Engineered Materials, Materials Processing, Materials Characterization, Materials for Microsystems, and Materials Modeling and Simulation. We believe these highlights collectively demonstrate the importance that a strong materials-science base has on the ultimate success of the NW program and the overall DOE technology portfolio.

  13. Precursor systems analyses of automated highway systems. Activity Area A: Urban and rural ahs analysis. Resource materials. Final report, August 1993-November 1994

    SciTech Connect (OSTI)

    Preston, H.; Holstein, J.; Ottesen, J.; Hoffman, P.

    1995-11-01

    The identification of technical, operational, and safety issues was accomplished primarily through a comprehensive literature search and a series of expert workshops. The literature search included identification and review of a broad range of previous AHS, IVHS, and related topic research and findings. This work supported a preliminary identification and/or confirmation and detailed description of major technical features, for example, (1) geometric design characteristics such as interchange design, lane width, and median configuration and (2) vehicle characteristics such as braking and acceleration capabilities. Accident type and severity data were also obtained and analyzed for various roadway categories and roadway improvements. Considering improved safety as a primary driver for the implementation of AHSs, current accident statistics were examined carefully to assess their potential utility as an indicator of likely AHS benefits. A summary of freeway design and operating characteristic information was developed not only to guide the ongoing work in this activity area, but to serve as a key point of reference for the team`s other seven activity areas throughout the remainder of the program.

  14. HIGHWAY INFRASTRUCTURE FOCUS AREA NEXT-GENERATION INFRASTRUCTURE MATERIALS VOLUME I - TECHNICAL PROPOSAL & MANAGEMENTENHANCEMENT OF TRANSPORTATION INFRASTRUCTURE WITH IRON-BASED AMORPHOUS-METAL AND CERAMIC COATINGS

    SciTech Connect (OSTI)

    Farmer, J C

    2007-12-04

    The infrastructure for transportation in the United States allows for a high level of mobility and freight activity for the current population of 300 million residents, and several million business establishments. According to a Department of Transportation study, more than 230 million motor vehicles, ships, airplanes, and railroads cars were used on 6.4 million kilometers (4 million miles) of highways, railroads, airports, and waterways in 1998. Pipelines and storage tanks were considered to be part of this deteriorating infrastructure. The annual direct cost of corrosion in the infrastructure category was estimated to be approximately $22.6 billion in 1998. There were 583,000 bridges in the United States in 1998. Of this total, 200,000 bridges were steel, 235,000 were conventional reinforced concrete, 108,000 bridges were constructed using pre-stressed concrete, and the balance was made using other materials of construction. Approximately 15 percent of the bridges accounted for at this point in time were structurally deficient, primarily due to corrosion of steel and steel reinforcement. Iron-based amorphous metals, including SAM2X5 (Fe{sub 49.7}Cr{sub 17.7}Mn{sub 1.9}Mo{sub 7.4}W{sub 1.6}B{sub 15.2}C{sub 3.8}Si{sub 2.4}) and SAM1651 (Fe{sub 48}Mo{sub 14}Cr{sub 15}Y{sub 2}C{sub 15}B{sub 6}) have been developed, and have very good corrosion resistance. These materials have been prepared as a melt-spun ribbons, as well as gas atomized powders and thermal-spray coatings. During electrochemical testing in several environments, including seawater at 90 C, the passive film stabilities of these materials were found to be comparable to that of more expensive high-performance alloys, based on electrochemical measurements of the passive film breakdown potential and general corrosion rates. These materials also performed very well in standard salt fog tests. Chromium (Cr), molybdenum (Mo) and tungsten (W) provided corrosion resistance, and boron (B) enabled glass formation. The high boron content of this particular amorphous metal made it an effective neutron absorber, and suitable for criticality control applications. These amorphous alloys appear to maintain their corrosion resistance up to the glass transition temperature. Visionary research is proposed to extend the application of corrosion-resistant iron-based amorphous metal coatings, and variants of these coatings, to protection of the Nation's transportation infrastructure. Specific objectives of the proposed work are: (1) fabrication of appropriate test samples for evaluation of concept; (2) collection of production and test data for coated steel reinforcement bars, enabling systematic comparison of various coating options, based upon performance and economic considerations; and (3) construction and testing of concrete structures with coated steel reinforcement bars, thereby demonstrating the value of amorphous-metal coatings. The benefits of ceramic coatings as thermal barriers will also be addressed.

  15. Adventures in scientific nuclear diplomacy

    SciTech Connect (OSTI)

    Hecker, Siegfried S.

    2014-05-09

    A former director of Los Alamos National Laboratory offers a first-person perspective on the important contributions scientists can make toward improving the safety and security of nuclear materials and reducing the global nuclear dangers in an evolving world.

  16. Hot Leg Piping Materials Issues

    SciTech Connect (OSTI)

    V. Munne

    2006-07-19

    With Naval Reactors (NR) approval of the Naval Reactors Prime Contractor Team (NRPCT) recommendation to develop a gas cooled reactor directly coupled to a Brayton power conversion system as the space nuclear power plant (SNPP) for Project Prometheus (References a and b) the reactor outlet piping was recognized to require a design that utilizes internal insulation (Reference c). The initial pipe design suggested ceramic fiber blanket as the insulation material based on requirements associated with service temperature capability within the expected range, very low thermal conductivity, and low density. Nevertheless, it was not considered to be well suited for internal insulation use because its very high surface area and proclivity for holding adsorbed gases, especially water, would make outgassing a source of contaminant gases in the He-Xe working fluid. Additionally, ceramic fiber blanket insulating materials become very friable after relatively short service periods at working temperatures and small pieces of fiber could be dislodged and contaminate the system. Consequently, alternative insulation materials were sought that would have comparable thermal properties and density but superior structural integrity and greatly reduced outgassing. This letter provides technical information regarding insulation and materials issues for the Hot Leg Piping preconceptual design developed for the Project Prometheus space nuclear power plant (SNPP).

  17. NCS area of applicability determination for AVLIS

    SciTech Connect (OSTI)

    Gross, C.; Koopman, R.P.

    1999-07-01

    The authors present a method for examining congruence between the processes that make up an AVLIS enrichment plant and the benchmark critical experiments that are used to establish the bias and validate the codes used for nuclear criticality safety (NCS) calculations of those processes. A measure of the validity of the process of selecting critical experiments that are similar in nature to processes found in the plant is presented. The probability of fission depends primarily on neutron energy and the interaction cross sections of the materials in the process. The physics of fission has led one to consider the energy of neutrons causing fission to be the fundamental parameter for examining the area of applicability. Benchmark experiments are chosen to cover the material compositions, geometric arrangements, neutron energy spectra, and other parameters such as material heterogeneity, neutron leakage or reflection, interaction, and absorption in special materials. These parameters influence the process by affecting the number of neutrons available to cause fission at any given energy. The neutron energy distribution is established primarily as a result of the energy-dependent cross sections for the materials that are present. Thus, the energy of neutrons causing fission is the fundamental parameter needed for examining the effects of other parameters within the area of applicability.

  18. Spent Fuel Working Group report on inventory and storage of the Department`s spent nuclear fuel and other reactor irradiated nuclear materials and their environmental, safety and health vulnerabilities. Volume 2, Working Group Assessment Team reports; Vulnerability development forms; Working group documents

    SciTech Connect (OSTI)

    Not Available

    1993-11-01

    The Secretary of Energy`s memorandum of August 19, 1993, established an initiative for a Department-wide assessment of the vulnerabilities of stored spent nuclear fuel and other reactor irradiated nuclear materials. A Project Plan to accomplish this study was issued on September 20, 1993 by US Department of Energy, Office of Environment, Health and Safety (EH) which established responsibilities for personnel essential to the study. The DOE Spent Fuel Working Group, which was formed for this purpose and produced the Project Plan, will manage the assessment and produce a report for the Secretary by November 20, 1993. This report was prepared by the Working Group Assessment Team assigned to the Hanford Site facilities. Results contained in this report will be reviewed, along with similar reports from all other selected DOE storage sites, by a working group review panel which will assemble the final summary report to the Secretary on spent nuclear fuel storage inventory and vulnerability.

  19. Critical Materials:

    Office of Environmental Management (EM)

    Critical Materials: 1 Technology Assessment 2 Contents 3 1. Introduction to the Technology/System ............................................................................................... 2 4 2. Technology Assessment and Potential ................................................................................................. 5 5 2.1 Major Trends in Selected Clean Energy Application Areas ........................................................... 5 6 2.1.1 Permanent Magnets for Wind

  20. Radiation Damage/Materials Modification

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Radiation Damage/Materials Modification High-energy ion irradiation is an important tool for studying radiation damage effects Materials in a nuclear reactor are exposed to extreme temperature and radiation conditions that degrade their physical properties to the point of failure. For example, alpha-decay in nuclear fuels results in dislocation damage to and accumulation of helium and fission gasses in the material. Similarly, neutrons interacting with non-nuclear components can displace atoms

  1. Material Balance Report | Department of Energy

    Office of Environmental Management (EM)

    Material Balance Report Material Balance Report Form supports nuclear material control and accountability. PDF icon Material Balance Report More Documents & Publications DOE/NRC F 742 PHYSICAL INVENTORY LISTING DOE/NRC F 740M

  2. Some thoughts on the nonproliferation of nuclear weapons

    SciTech Connect (OSTI)

    Krikorian N.H.; Hawkins, H.T.

    1996-05-01

    This paper discusses factors controlling the dissemination of nuclear technologies and especially fissile materials.

  3. Material Protection, Accounting and Control

    Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

    and future U.S. nuclear fuel cycles, to manage and minimize proliferation and terrorism risk. n Objectives * Develop and demonstrate advanced material control and ...

  4. ENVIRONMENTAL SCIENCES; ENVIRONMENTAL MATERIALS; CONTAMINATION...

    Office of Scientific and Technical Information (OSTI)

    audit of SRP radioactive waste Ashley, C. 05 NUCLEAR FUELS; 54 ENVIRONMENTAL SCIENCES; ENVIRONMENTAL MATERIALS; CONTAMINATION; RADIOACTIVE EFFLUENTS; EMISSION; HIGH-LEVEL...

  5. Nuclear Safety Information Agreement Between the U.S. Nuclear...

    Broader source: Energy.gov (indexed) [DOE]

    Environment, Health, Safety and Security (EHSS DOE), Cathy Haney (Director, Office of Nuclear Materials Safety and Safeguards (NRC)), Marissa Bailey (Director, Division of Fuel...

  6. ORISE: Preparing Nations to Fight Nuclear Smuggling

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    smuggling remains a global security threat. How ORISE is Making a Difference Recent seizures of weapon-grade nuclear materials suggest such materials remain in illegal...

  7. ORISE: Preparing Nations to Fight Nuclear Smuggling

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Preventing Nuclear Smuggling Program ORISE helps other nations to fight theft of nuclear materials With the knowledge needed to incorporate radiological materials in an explosive device now widely available and unsecured stockpiles still a reality, nuclear smuggling remains a global security threat. How ORISE is Making a Difference Recent seizures of weapon-grade nuclear materials suggest such materials remain in illegal circulation and could be used to kill tens or hundreds of thousands of

  8. Nuclear Regulatory Commission information digest

    SciTech Connect (OSTI)

    None,

    1990-03-01

    The Nuclear Regulatory Commission information digest provides summary information regarding the US Nuclear Regulatory Commission, its regulatory responsibilities, and areas licensed by the commission. This is an annual publication for the general use of the NRC Staff and is available to the public. The digest is divided into two parts: the first presents an overview of the US Nuclear Regulatory Commission and the second provides data on NRC commercial nuclear reactor licensees and commercial nuclear power reactors worldwide.

  9. Joint China-United States Report for Year 1 Insulation Materials and Systems Project Area Clean Energy Research Center Building Energy Efficiency (CERC-BEE)

    SciTech Connect (OSTI)

    Stovall, Therese K; Biswas, Kaushik; Song, Bo; Zhang, Sisi

    2012-08-01

    In November of 2009, the presidents of China and the U.S. announced the establishment of the Clean Energy Research Center (CERC). This broad research effort is co-funded by both countries and involves a large number of research centers and universities in both countries. One part of this program is focused on improving the energy efficiency of buildings. One portion of the CERC-BEE was focused on building insulation systems. The research objective of this effort was to Identify and investigate candidate high performance fire resistant building insulation technologies that meet the goal of building code compliance for exterior wall applications in green buildings in multiple climate zones. A Joint Work Plan was established between researchers at the China Academy of Building Research and Oak Ridge National Laboratory. Efforts in the first year under this plan focused on information gathering. The objective of this research program is to reduce building energy use in China via improved building insulation technology. In cold regions in China, residents often use inefficient heating systems to provide a minimal comfort level within inefficient buildings. In warmer regions, air conditioning has not been commonly used. As living standards rise, energy consumption in these regions will increase dramatically unless significant improvements are made in building energy performance. Previous efforts that defined the current state of the built environment in China and in the U.S. will be used in this research. In countries around the world, building improvements have typically followed the implementation of more stringent building codes. There have been several changes in building codes in both the U.S. and China within the last few years. New U.S. building codes have increased the amount of wall insulation required in new buildings. New government statements from multiple agencies in China have recently changed the requirements for buildings in terms of energy efficiency and fire safety. A related issue is the degree to which new standards are adopted and enforced. In the U.S., standards are developed using a consensus process, and local government agencies are free to implement these standards or to ignore them. For example, some U.S. states are still using 2003 versions of the building efficiency standards. There is also a great variation in the degree to which the locally adopted standards are enforced in different U.S. cities and states. With a more central process in China, these issues are different, but possible impacts of variable enforcement efficacy may also exist. Therefore, current building codes in China will be compared to the current state of building fire-safety and energy-efficiency codes in the U.S. and areas for possible improvements in both countries will be explored. In particular, the focus of the applications in China will be on green buildings. The terminology of 'green buildings' has different meanings to different audiences. The U.S. research is interested in both new, green buildings, and on retrofitting existing inefficient buildings. An initial effort will be made to clarify the scope of the pertinent wall insulation systems for these applications.

  10. Nonproliferation | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    dispose of dangerous nuclear and radiological material, and detect and control the proliferation of related WMD technology and expertise. Vietnam Removal Working in close...

  11. Nuclear Science

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    Nuclear Science Nuclear Science Experimental and theoretical nuclear research carried out at NERSC is driven by the quest for improving our understanding of the building blocks of...

  12. Model Action Plan for Nuclear Forensics and Nuclear Attribution

    SciTech Connect (OSTI)

    Dudder, G B; Niemeyer, S; Smith, D K; Kristo, M J

    2004-03-01

    Nuclear forensics and nuclear attribution have become increasingly important tools in the fight against illegal trafficking in nuclear and radiological materials. This technical report documents the field of nuclear forensics and nuclear attribution in a comprehensive manner, summarizing tools and procedures that have heretofore been described independently in the scientific literature. This report also provides national policy-makers, decision-makers, and technical managers with guidance for responding to incidents involving the interdiction of nuclear and radiological materials. However, due to the significant capital costs of the equipment and the specialized expertise of the personnel, work in the field of nuclear forensics has been restricted so far to a handful of national and international laboratories. In fact, there are a limited number of specialists who have experience working with interdicted nuclear materials and affiliated evidence. Most of the laboratories that have the requisite equipment, personnel, and experience to perform nuclear forensic analysis are participants in the Nuclear Smuggling International Technical Working Group or ITWG (see Section 1.8). Consequently, there is a need to disseminate information on an appropriate response to incidents of nuclear smuggling, including a comprehensive approach to gathering evidence that meets appropriate legal standards and to developing insights into the source and routes of nuclear and radiological contraband. Appendix A presents a ''Menu of Options'' for other Member States to request assistance from the ITWG Nuclear Forensics Laboratories (INFL) on nuclear forensic cases.

  13. An Overview of the Regulation of Low Dose Radiation in the Nuclear and Non-nuclear Industries

    SciTech Connect (OSTI)

    Menon, Shankar; Valencia, Luis; Teunckens, Lucien

    2003-02-27

    Now that increasing numbers of nuclear power stations are reaching the end of their commercially useful lives, the management of the large quantities of very low level radioactive material that arises during their decommissioning has become a major subject of discussion, with very significant economic implications. Much of this material can, in an environmentally advantageous manner, be recycled for reuse without radiological restrictions. Much larger quantities--2-3 orders of magnitude larger--of material, radiologically similar to the candidate material for recycling from the nuclear industry, arise in non-nuclear industries like coal, fertilizer, oil and gas, mining, etc. In such industries, naturally occurring radioactivity is artificially concentrated in products, by-products or waste to form TENORM (Technologically Enhanced Naturally Occurring Radioactive Material). It is only in the last decade that the international community has become aware of the prevalence of TENORM, specially the activity levels and quantities arising in so many non-nuclear industries. The first reaction of international organizations seems to have been to propose different standards for the nuclear and non-nuclear industries, with very stringent release criteria for radioactive material from the regulated nuclear industry and up to thirty to a hundred times more liberal criteria for the release/exemption of TENORM from the as yet unregulated non-nuclear industries. There are significant strategic issues that need to be discussed and resolved. Some examples of these are: - Disposal aspects of long-lived nuclides, - The use of radioactive residues in building materials, - Commercial aspects of differing and discriminating criteria in competing power industries in a world of deregulated electric power production. Of even greater importance is the need for the discussion of certain basic issues, such as - The quantitative risk levels of exposure to ionizing radiation, - The need for in-depth studies on populations of the naturally high background dose level areas of the world, - The validity of the various calculation codes currently used to arrive at mass specific clearance levels for redundant material. The paper discusses these and other strategic issues regarding the management of redundant low radiation material from both the nuclear and non-nuclear industries, underlining the need for consistency in regulatory treatment.

  14. Material Management/Strategic Reserve | Y-12 National Security Complex

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    ... Material Management/Strategic Reserve Y-12 ensures safe, secure and compliant storage of the nation's strategic reserve of nuclear materials at Y-12. Our Nuclear Materials Management and Storage Program receives, stores, protects, dispositions and manages strategic and special nuclear materials and provides programmatic planning, analysis and forecasting for national security material requirements supporting Stockpile Stewardship and other DOE programs

  15. Performance Assessment and Composit Analysis Material Disposal...

    Office of Environmental Management (EM)

    Performance Assessment and Composit Analysis Material Disposal Area G Revision 4 Performance Assessment and Composit Analysis Material Disposal Area G Revision 4 Los Alamos...

  16. Serious Materials | Open Energy Information

    Open Energy Info (EERE)

    Serious Materials Jump to: navigation, search Name: Serious Materials Address: 1250 Elko Drive Place: Sunnyvale, California Zip: 94089 Region: Bay Area Sector: Carbon Product:...

  17. UNCLASSIFIED Institute for Materials ...

    Broader source: All U.S. Department of Energy (DOE) Office Webpages (Extended Search)

    properties. In this talk, I will discuss our recent research in the area of nanoscale materials modeling, using various atomistic simulation techniques, aimed at uncovering the...

  18. Improving the Safeguardability of Nuclear Facilities

    SciTech Connect (OSTI)

    T. Bjornard; R. Bari; D. Hebditch; P. Peterson; M. Schanfein

    2009-07-01

    The application of a Safeguards-by-Design (SBD) process for new nuclear facilities has the potential to reduce security risks and proliferation hazards while improving the synergy of major design features and raising operational efficiency, in a world where significant expansion of nuclear energy use may occur. Correspondingly, the U.S. DOEs Next Generation Safeguards Initiative (NGSI) includes objectives to contribute to international efforts to develop SBD, and to apply SBD in the development of new U.S. nuclear infrastructure. Here, SBD is defined as a structured approach to ensure the timely, efficient and cost effective integration of international safeguards and other nonproliferation barriers with national material control and accountability, physical protection, and safety objectives into the overall design process for a nuclear facility, from initial planning through design, construction and operation. The SBD process, in its simplest form, may be applied usefully today within most national regulatory environments. Development of a mature approach to implementing SBD requires work in the areas of requirements definition, design processes, technology and methodology, and institutionalization. The U.S. efforts described in this paper are supportive of SBD work for international safeguards that has recently been initiated by the IAEA with the participation of many stakeholders including member States, the IAEA, nuclear technology suppliers, nuclear utilities, and the broader international nonproliferation community.

  19. Independent Review of Pantex Plant Property and Material Clearance Processes September 8-12, 2008

    Energy Savers [EERE]

    Suspension on Release of Uncontaminated Scrap from DOE Radiological Areas Current Status and Strategies for Management Richard W. Meehan National Nuclear Security Administration Office of Nuclear Material Integration Presentation to: EM Site Specific Advisory Board Chairs November 5, 2013 2 * Moratorium and Suspension policies were instituted in February and January of 2000 * "Moratorium" applies ONLY to metals contaminated in volume through activation or melt consolidation. *

  20. Materials characterisation with the associated particle technique

    SciTech Connect (OSTI)

    Perot, Bertrand; Carasco, Cedric; Deyglun, Clement; Eleon, Cyrille; Mariani, Alain; Ma, Jean-Luc

    2012-07-01

    Since the last past years, the Nuclear Measurement Laboratory of CEA Cadarache, France, together with Partners from European and National projects, has been studying the application of fast neutron interrogation with the Associated Particle Technique for material identification in different areas of homeland and maritime security, and for the characterisation of the materials constituting radioactive waste. Fast 14 MeV neutrons are produced from the H-3(H-2,n)alpha fusion reaction in a sealed tube neutron generator embedding an alpha detector. The alpha particle is used to tag neutron direction and emission time, thus allowing the electronic selection of neutron-induced gamma spectra in the voxels of interest. Gamma rays emitted by tagged neutron interactions on the present nuclei (C, O, N, Fe, Al, Si, Cl, etc.) are recorded with spectroscopic detectors and analysed to determine elemental proportions, thus allowing material identification. Investigations have been conducted for the detection of explosives, illicit drugs and contraband materials in cargo containers, for the inspection of objects lying on the sea floor suspected to contain explosives like mines, bombs, torpedoes, etc., for the recognition of an improvised chemical device, and for material identification in radioactive waste packages. Recently the detection of special nuclear materials is being investigated using time correlation analysis between induced fission particles, instead of gamma-ray spectroscopy. The paper presents an overview of these studies and last results. (authors)