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Note: This page contains sample records for the topic "nuclear material control" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


1

Nuclear Materials Control and Accountability  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

data and reports on accountable nuclear material to NMMSS and Nuclear Materials Inventory Assessments.", to "The accounting system provides data for reporting on accountable...

2

Nuclear Material Control and Accountability  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

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 Table of Changes Page/Section Change Page 57/Section 6.4.4.1. Change from, - Accounting records and source documents shall include item identification, material type, form, quantity, location, gross

3

Nuclear Materials Control and Accountability  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

JUNE 2011 JUNE 2011 ──────────────── CHANGE NOTICE NO.1 AUGUST 2011 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. 1 DOE -STD-1194-2011 August 2011 Nuclear Materials Control and Accountability Table of Changes Page/Section Change Title Page Formatting and font size adjusted. Page 2/Section 4.h. Reference to document was updated from DOE M 470.4-1 Chg 2, Safeguards and Security Program Planning and Management, dated 10-2-10 to DOE O 470.4B, Safeguards and Security Program, dated 7-21-11. Page 2/Section 4.i. Reference to document was updated from DOE M

4

Nuclear Materials Control and Accountability  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

June 2011 June 2011 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. DOE-STD-1194-2011 i This page is intentionally left blank. DOE-STD-1194-2011 ii TABLE OF CONTENTS FOREWORD ..................................................................................................................................................................................... iii 1 . S C O P E ........................................................................................................................................................................................... 1 2

5

Material Control & Accountability | National Nuclear Security  

NLE Websites -- All DOE Office Websites (Extended Search)

Control & Accountability | National Nuclear Security Control & Accountability | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Material Control & Accountability Home > About Us > Our Programs > Nuclear Security > Material Control & Accountability Material Control & Accountability Safeguards First Principles Initiative

6

Material Control & Accountability | National Nuclear Security  

National Nuclear Security Administration (NNSA)

Control & Accountability | National Nuclear Security Control & Accountability | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Material Control & Accountability Home > About Us > Our Programs > Nuclear Security > Material Control & Accountability Material Control & Accountability Safeguards First Principles Initiative

7

The nuclear materials control technology briefing book  

SciTech Connect

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.

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

1992-03-01T23:59:59.000Z

8

Measurement control administration for nuclear materials accountability  

Science Conference Proceedings (OSTI)

In 1986 a measurement control program was instituted at Mound to ensure that measurement performance used for nuclear material accountability was properly monitored and documented. The organization and management of various aspects of the program are discussed. Accurate measurements are the basis of nuclear material accountability. The validity of the accountability values depends on the measurement results that are used to determine inventories, receipts, and shipments. With this measurement information, material balances are calculated to determine losses and gains of materials during a specific time period. Calculation of Inventory Differences (ID) are based on chemical or physical measurements of many items. The validity of each term is dependent on the component measurements. Thus, in Figure 1, the measured element weight of 17 g is dependent on the performance of the particular measurement system that was used. In this case, the measurement is performed using a passive gamma ray method with a calibration curve determined by measuring representative standards containing a range of special nuclear materials (Figure 2). One objective of a measurement control program is to monitor and verify the validity of the calibration curve (Figure 3). In 1986 Mound's Nuclear Materials Accountability (NMA) group instituted a formal measurement control program to ensure the validity of the numbers that comprise this equation and provide a measure of how well bulk materials can be controlled. Most measurements used for accountability are production measurements with their own quality assurance programs. In many cases a measurement control system is planned and maintained by the developers and operators of the particular measurement system with oversight by the management responsible for the results. 4 refs., 7 figs.

Rudy, C.R.

1991-01-31T23:59:59.000Z

9

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

National Nuclear Security Administration (NNSA)

Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs...

10

Nuclear Material Control and Accountability System Effectiveness Tool (MSET)  

SciTech Connect

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.

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

2011-01-01T23:59:59.000Z

11

DOE O 474.2 Admin Chg 2, Nuclear Material Control and Accountability  

Directives, Delegations, and Requirements

This Order establishes performance objectives, metrics, and requirements for developing, implementing, and maintaining a nuclear material control and ...

2011-06-27T23:59:59.000Z

12

Nuclear Materials  

Science Conference Proceedings (OSTI)

Materials and Fuels for the Current and Advanced Nuclear Reactors III ... response of oxide ceramics for nuclear applications through experiment, theory, and...

13

ADMINISTRATIVE CHANGE TO DOE O 474.2, NUCLEAR MATERIAL CONTROL...  

National Nuclear Security Administration (NNSA)

Chg 1: 8-3-2011 NUCLEAR MATERIAL CONTROL AND ACCOUNTABILITY U.S. DEPARTMENT OF ENERGY Office of Health, Safety and Security DOE O 474.2 DOE O 474.2 1 6-27-2011 NUCLEAR...

14

Program on Technology Innovation: Controlled Recycling of Contaminated Materials for Nuclear Industry Uses  

Science Conference Proceedings (OSTI)

This report addresses opportunities to recycle materials in radioactive waste by decontamination and fabrication into new components for use in the nuclear industry. In particular, a novel approach called "controlled recycling" involves a procedure that controls the material during decontamination, metal processing and remanufacture into components for reuse in the nuclear industry.

2006-11-09T23:59:59.000Z

15

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

National Nuclear Security Administration (NNSA)

Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

16

An English/Chinese and Chinese/English glossary for nuclear material control and accounting  

SciTech Connect

This document is a glossary of English/Chinese and Chinese/English expressions which are technical terms likely to occur in literature related to nuclear materials control and accounting.

Agnew, C.

1998-12-31T23:59:59.000Z

17

Comprehensive Nuclear Materials  

Science Conference Proceedings (OSTI)

This book encompasses a rich seam of current information on the vast and multidisciplinary field of nuclear materials employed in fission and prototype fusion systems. Discussion includes both historical and contemporary international research in nuclear materials, from Actinides to Zirconium alloys, from the worlds leading scientists and engineers. Synthesizes pertinent current science to support the selection, assessment, validation and engineering of materials in extreme nuclear environments. The work discusses the major classes of materials suitable for usage in nuclear fission, fusion reactors and high power accelerators, and for diverse functions in fuels, cladding, moderator and control materials, structural, functional, and waste materials.

Konings, Dr. Rudy J. M. [European Commission Joint Research Centre; Allen, Todd R. [University of Wisconsin, Madison; Stoller, Roger E [ORNL; Yamanaka, Prof. Shinsuke [Osaka University

2012-01-01T23:59:59.000Z

18

Nuclear materials control technology in the post-cold war world: Radiation-based methods and information management systems  

SciTech Connect

The end of the cold war is providing both opportunities and requirements for improving the control of nuclear materials around the world. The dismantlement of nuclear weapons and the growth of nuclear power, including the use of plutonium in light water reactors and breeder reactor programs, coupled with enhanced proliferation concerns, drive the need for improved nuclear materials control. We describe nuclear materials control and the role of technology in making controls more effective and efficient. The current use and anticipated development in selected radiation-based methods and related information management systems am described briefly.

Tape, J.W.; Eccleston, G.W.; Ensslin, N.; Markin, J.T.

1993-06-01T23:59:59.000Z

19

Nuclear Materials  

Science Conference Proceedings (OSTI)

Assessing the Thermal Stability of Bulk Metallic Glasses for Nuclear Waste Applications by K. Hildal, J.H. Perepezko, and L. Kaufman, $10.00 ($10.00), $25.00.

20

Where do the Nuclear Materials Management functions fit in the Materials Control and Accountability (MC and A) plan  

Science Conference Proceedings (OSTI)

Safeguards had its beginning in the early 1940s and has continued to grow through the stormy years in dealing with nuclear materials. MC and A Plans have been developed for each facility which includes requirements for containment, surveillance, internal controls, measurements, statistics, records and report systems, and inventory certification of its nuclear materials, in the context of how precisely the inventory is known at stated risk or confidence levels. The I and E Regulations, the newest document affecting the control system, are used for testing the current MC and A plan in place at each facility. Nuclear Materials Management activities also have reporting requirements that include: (1) Annual Forecast, (2) Materials Management Plan, (3) Quarterly Status Report, (4) Assessment Report, and (5) Scrap and Excess Material Management. Data used to generate reports for both functions come from the same data base and source documents at most facilities. The separation of sponsoring groups at the DOE for NM Accountability and NM Management can and does pose problems for contractors. In this paper, we will try to separate and identify these overlaps at the Facility and DOE level.

DeVer, E.A.

1987-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear material control" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Nuclear Material Management Abstract  

Science Conference Proceedings (OSTI)

Nevada Test Site (NTS) has transitioned from its historical and critical role of weapons testing to another critical role for the nation. This new role focuses on being a integral element in solving the multiple challenges facing the National Nuclear Security Administration (NNSA) with nuclear material management. NTS is positioned to be a solution for other NNSA sites challenged with safe nuclear materials storage and disposition. NNSA, with site involvement, is currently transforming the nuclear stockpile and supporting infrastructure to meet the 2030 vision. Efforts are under way to consolidate and modernize the production complex . With respect to the nuclear material stockpile, the NNSA sites are currently reducing the complex nuclear material inventory through disposition and consolidation. This includes moving material from other sites to NTS. State of the art nuclear material management and control practices at NTS are essential for NTS to ensure that assigned activities are accomplished in a safe, secure, efficient, and environmentally responsible manner. NTS activities and challenges will be addressed.

Jesse C. Schreiber

2007-07-10T23:59:59.000Z

22

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

Science Conference Proceedings (OSTI)

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.

Not Available

1981-10-01T23:59:59.000Z

23

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

SciTech Connect

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.

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

1995-05-01T23:59:59.000Z

24

Upgrade of the Nuclear Material Protection, Control and Accounting System at the VNIIEF Industrial Zone  

Science Conference Proceedings (OSTI)

The Industrial Zone at the Russian Federal Nuclear Center/All-Russian Scientific Research Institute of Experimental Physics (RFNC/VNEEF) consists of ten guarded areas with twenty two material balance areas (A and As). The type of facilities in the Industrial Zone include storage sites, machine shops, research facilities, and training facilities. Modernization of the Material Protection, Control and Accounting (MPC and A) System at the Industrial Zone started in 1997. This paper provides a description of, the methodology/strategy used in the upgrade of the MFC and A system.

Lewis, J.C.; Maltsev, V.; Singh, S.P.

1999-09-20T23:59:59.000Z

25

Nuclear Materials Committee  

Science Conference Proceedings (OSTI)

The Nuclear Materials Committee is part of the Structural Materials Division. Our Mission: Includes the scientific and technical aspects of materials which are...

26

FIRST SODIUM REACTOR EXPERIMENT (SRE) TEST OF HALLAM NUCLEAR POWER FACILITY (HNPF) CONTROL MATERIALS  

SciTech Connect

An experiment was conducted in the SRE to measure temperatures and neutron flux levels in and near a boron-containing simulated control rod. The data are being used to check analytical methods developed for prediction of control rod heat generation rates and maximum temperatures in this type of control rod in the Hallam Nuclear Power Facility. The maximum observed temperatures with a reactor power level of 20 Mw were 1363 deg F for a boron-- nickel alloy ring having a 0.105-in. radial clearance with the thimble and 1100 deg F for a boron -nickel alloy ring having a 0.020-in. radial clearance. The maximum temperature difference between the coolant and the control rod was 473 deg F. It is concluded that the expected greater heat generation rates in the Hallam reactor would prohibit the use of boron-containing absorber materials in a combined a him-safety rod. (auth)

Arneson, S.O.

1959-06-01T23:59:59.000Z

27

Nuclear Materials Management & Safeguards System | National Nuclear...  

National Nuclear Security Administration (NNSA)

Management & Safeguards System Nuclear Materials Management & Safeguards System NMMSS U.S. Department of Energy U.S. Nuclear Regulatory Commission Nuclear Materials...

28

Nuclear Materials Management & Safeguards System | National Nuclear...  

NLE Websites -- All DOE Office Websites (Extended Search)

Our Jobs Our Jobs Working at NNSA Blog Nuclear Materials Management & Safeguards System Home > About Us > Our Programs > Nuclear Security > Nuclear Materials Management &...

29

Nuclear Materials Management & Safeguards System | National Nuclear...  

National Nuclear Security Administration (NNSA)

System Nuclear Materials Management & Safeguards System NMMSS U.S. Department of Energy U.S. Nuclear Regulatory Commission Nuclear Materials Management & Safeguards System...

30

NUCLEAR MATERIALS ACCOUNTING SYSTEMSMODERNIZATION INITIATIVE...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NUCLEAR MATERIALS ACCOUNTING SYSTEMSMODERNIZATION INITIATIVE, IG-0556 NUCLEAR MATERIALS ACCOUNTING SYSTEMSMODERNIZATION INITIATIVE, IG-0556 The Department of Energy (Department),...

31

Absolute nuclear material assay  

DOE Patents (OSTI)

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.

Prasad, Manoj K. (Pleasanton, CA); Snyderman, Neal J. (Berkeley, CA); Rowland, Mark S. (Alamo, CA)

2010-07-13T23:59:59.000Z

32

Absolute nuclear material assay  

DOE Patents (OSTI)

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.

Prasad, Manoj K. (Pleasanton, CA); Snyderman, Neal J. (Berkeley, CA); Rowland, Mark S. (Alamo, CA)

2012-05-15T23:59:59.000Z

33

Standard guide for application of radiation monitors to the control and physical security of special nuclear material  

E-Print Network (OSTI)

1.1 This guide briefly describes the state-of-the-art of radiation monitors for detecting special nuclear material (SNM) (see 3.1.11) in order to establish the context in which to write performance standards for the monitors. This guide extracts information from technical documentation to provide information for selecting, calibrating, testing, and operating such radiation monitors when they are used for the control and protection of SNM. This guide offers an unobtrusive means of searching pedestrians, packages, and motor vehicles for concealed SNM as one part of a nuclear material control or security plan for nuclear materials. The radiation monitors can provide an efficient, sensitive, and reliable means of detecting the theft of small quantities of SNM while maintaining a low likelihood of nuisance alarms. 1.2 Dependable operation of SNM radiation monitors rests on selecting appropriate monitors for the task, operating them in a hospitable environment, and conducting an effective program to test, calibrat...

American Society for Testing and Materials. Philadelphia

1999-01-01T23:59:59.000Z

34

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

SciTech Connect

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.

Not Available

1984-06-01T23:59:59.000Z

35

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

SciTech Connect

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.

Not Available

1986-06-01T23:59:59.000Z

36

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

SciTech Connect

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.

1986-06-01T23:59:59.000Z

37

NUCLEAR FUEL MATERIAL  

DOE Patents (OSTI)

An improved method is given for making the carbides of nuclear fuel material. The metal of the fuel material, which may be a fissile and/or fertile material, is transformed into a silicide, after which the silicide is comminuted to the desired particle size. This silicide is then carburized at an elevated temperature, either above or below the melting point of the silicide, to produce an intimate mixture of the carbide of the fuel material and the carbide of silicon. This mixture of the fuel material carbide and the silicon carbide is relatively stable in the presence of moisture and does not exhibit the highly reactive surface condition which is observed with fuel material carbides made by most other known methods. (AEC)

Goeddel, W.V.

1962-06-26T23:59:59.000Z

38

The Ural Electrochemical Integrated Plant Sustainability Program of Nuclear Material Protection, Control and Accounting System Upgrades  

Science Conference Proceedings (OSTI)

UEIP has been working on a comprehensive sustainability program that includes establishing a site sustainability working group, information gathering, planning, organizing, developing schedule and estimated costs, trhough joint UEIP-US DOE/NNSA National Laboratory sustainability contracts. Considerable efforts have been necessary in the sustainability planning, monitoring, and control of the scope of work using tools such as Microsoft Excel, Microsoft Project and SAP R/3. While information interchanges within the sustainability program provides adequate US assurances that US funds are well spent through its quarterly reporting methodology, proper information security and protection measures are taken throughout the process. Decommissioning of outdated equipment has also become part of determining sustainability requirements and processes. The sites sustainability program has facilitated the development of a transition plan toward eventual full Russian funding of sustaining nuclear security upgrades.

Vakhonin, Alexander; Yuldashev, Rashid; Dabbs, Richard D.; Carroll, Michael F.; Garrett, Albert G.; Patrick, Scott W.; Ku, Eshter M.

2009-09-30T23:59:59.000Z

39

Special Topics: Nuclear Materials: Videos  

Science Conference Proceedings (OSTI)

The Living Textbook of Nuclear Chemistry, ACS. ... Webcast on response of structural materials in nuclear power systems to irradiation, 0, 761, Cathy Rohrer ...

40

Materials for Nuclear Power: Digital Resource Center ...  

Science Conference Proceedings (OSTI)

Select, Sandbox, Open Discussion Regarding Materials for Nuclear Power ... Nuclear Power Background, Trends in Nuclear Power, The Nuclear Fuel Cycle...

Note: This page contains sample records for the topic "nuclear material control" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

NUCLEAR MATERIAL PACKAGING MANUAL  

E-Print Network (OSTI)

The enclosed copy ofdraft DOE Manual M44I.I, Nuclear Material Packaging Manual, is forwarded for your review and comment. This satisfies commitment 5.1-3 in Appendix o ofthe implementation plan (IP) for recommendation 2005-1, Nuclear Material Packaging. The next milestone in Section 5.1 ofthe 2005-1 IP is forwarding the manual to the DOE 2005-1 Technical Review Board (TRB) by April 30, 2006 to begin the final TRB review. Therefore, your comments are requested by April 21, 2006, in order to allow one week for resolution and updating the manual before it is sent to the TRB. Please contact me at 301-903-4407 ifyou have any questions. t

The Honorable; A. J. Eggenberger; M. Whitaker Dr-i

2006-01-01T23:59:59.000Z

42

Responsible stewardship of nuclear materials  

SciTech Connect

The ability to tap the massive energy potential of nuclear fission was first developed as a weapon to end a terrible world war. Nuclear fission is also a virtually inexhaustible energy resource, and is the only energy supply in certain areas in Russia, Kazakhstan and elsewhere. The potential link between civilian and military applications has been and continues to be a source of concern. With the end of the Cold War, this issue has taken a dramatic turn. The U.S. and Russia have agreed to reduce their nuclear weapons stockpiles by as much as two-thirds. This will make some 100 tonnes of separated plutonium and 500 tonnes of highly enriched uranium available, in a form that is obviously directly usable for weapons. The total world inventory of plutonium is now around 1000 tonnes and is increasing at 60-70 tonnes per year. There is even more highly enriched uranium. Fortunately the correct answer to what to do with excess weapons material is also the most attractive. It should be used and reused as fuel for fast reactors. Material in use (particularly nuclear material) is very easy to monitor and control, and is quite unattractive for diversion. Active management of fissile materials not only makes a major contribution to economic stability and well-being, but also simplifies accountability, inspection and other safeguards processes; provides a revenue stream to pay for the necessary safeguards; and, most importantly, limits the prospective world inventory of plutonium to only that which is used and useful.

Hannum, W.H.

1994-10-01T23:59:59.000Z

43

GKTC ACTIVITIES TO PROVIDE NUCLEAR MATERIAL PHYSICAL PROTECTION, CONTROL AND ACCOUNTING TRAINING FOR 2011-2012  

Science Conference Proceedings (OSTI)

The GKTC was created at the Kyiv Institute of Nuclear Research as a result of collaborative efforts between the United States and Ukraine. The GKTC has been designated by the Ukrainian Government to provide the MPC&A training and methodological assistance to nuclear facilities and nuclear specialists. In 2010 the GKTC has conducted the planned assessment of training needs of Ukrainian MPC&A specialists. The objective of this work is to acquire the detailed information about the number of MPC&A specialists and guard personnel, who in the coming years should receive the further advanced training. As a result of the performed training needs evaluation the GKTC has determined that in the coming years a number of new training courses need to be developed. Some training courses are already in the process of development. Also taking into account the specific of activity on the guarding of nuclear facilities, GKTC has begun to develop the specialized training courses for the guarding unit personnel. The evaluation of needs of training of Ukrainian specialists on the physical protection shows that without the technical base of learning is not possible to satisfy the needs of Ukrainian facilities, in particular, the need for further training of specialists who maintains physical protection technical means, provides vulnerability assessment and testing of technical means. To increase the training effectiveness and create the basis for specialized training courses holding the GKTC is now working on the construction of an Interior (non-classified) Physical Protection Training Site. The objective of this site is to simulate the actual conditions of the nuclear facility PP system including the complex of engineering and technical means that will help the GKTC training course participants to consolidate the knowledge and gain the practical skills in the work with PP system engineering and technical means for more effective performance of their official duties. This paper briefly describes the practical efforts applied to the provision of physical protection specialists advanced training in Ukraine and real results on the way to implement such efforts in 2011-2012.

Romanova, Olena; Gavrilyuk, Victor I.; Kirischuk, Volodymyr; Gavrilyuk-Burakova, Anna; Diakov, Oleksii; Drapey, Sergiy; Proskurin, Dmitry; Dickman, Deborah A.; Ferguson, Ken

2011-10-01T23:59:59.000Z

44

NUCLEAR REACTOR CONTROL SYSTEM  

DOE Patents (OSTI)

A control system is described for a nuclear reactor using enriched uranium fuel of the type of the swimming pool and other heterogeneous nuclear reactors. Circuits are included for automatically removing and inserting the control rods during the course of normal operation. Appropriate safety circuits close down the nuclear reactor in the event of emergency.

Epler, E.P.; Hanauer, S.H.; Oakes, L.C.

1959-11-01T23:59:59.000Z

45

Thermodynamic Database for Nuclear Materials  

Science Conference Proceedings (OSTI)

Feb 8, 2007 ... This resource features an interactive index to thermodynamic properties included on the International Nuclear Safety Center Material Properties...

46

SRS - Programs - Nuclear Materials Management  

NLE Websites -- All DOE Office Websites (Extended Search)

built in the mid-1950s, housed various Special Nuclear Materials missions including plutonium storage, shipping and handling; billet production for reactor target fabrication...

47

WEB RESOURCE: Nuclear Materials Database  

Science Conference Proceedings (OSTI)

Feb 12, 2007 ... Mechanical properties data for stainless steels and superalloys; mechanical properties data for nuclear materials as a database for research...

48

WSRC Nuclear Materials Cost Module  

National Nuclear Security Administration (NNSA)

Office (GAO) WSRC NM Cost Module Generates WSRC monthly and fiscal year to date Inventory and Manufacturing Statement for government owned accountable nuclear materials....

49

Nuclear Materials Management Program at the NNSS  

Science Conference Proceedings (OSTI)

The Nevada National Security Site (NNSS), formerly the Nevada Test Site, was established in 1951 mainly for weapons testing; because special nuclear materials (SNM) were expended during the tests, a nuclear material management program was not required. That changed in December 2004 with the receipt of Category I SNM for purposes other than weapons testing. At that time, Material Control and Accountability and Nuclear Material Management were a joint laboratory (Los Alamos and Lawrence Livermore) effort with nuclear material management being performed at the laboratories. That changed in March 2006 when the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office appointed sole responsibility to the Management and Operations (M&O) contractor, National Security Technologies, LLC (NSTec). Since 2006 the basic nuclear material management work was completed by a combination of M&O employees and subcontractors, but a true Nuclear Material Management (NMM) Program was not determined to be necessary until recently. With expanding missions and more nuclear material (NM) coming to the NNSS, it became imperative to have an organization to manage these materials; therefore, an NMM Manager was officially appointed by NSTec in 2012. In June 2011 a Gap Analysis and white paper was completed by a subcontractor; this presentation will include highlights from those documents along with our plans to resolve the gaps and stand up a functional and compliant NMM Program at the NNSS.

,

2012-06-08T23:59:59.000Z

50

Nuclear Resonance Fluorescence for Nuclear Materials Assay.  

E-Print Network (OSTI)

??This dissertation examines the measurement of nuclear resonance fluorescence gamma-rays as a technique to non-destructively determine isotopic compositions of target materials that are of interest (more)

Quiter, Brian Joseph

2010-01-01T23:59:59.000Z

51

WEB RESOURCE: Nuclear Materials and Nuclear Fuel/Waste  

Science Conference Proceedings (OSTI)

Feb 12, 2007 ... Select, Sandbox, Open Discussion Regarding Materials for Nuclear ... Trends in Nuclear Power, The Nuclear Fuel Cycle, Nuclear Science...

52

WEB RESOURCE: Transport Properties (Nuclear Materials)  

Science Conference Proceedings (OSTI)

Feb 12, 2007 ... Select, Sandbox, Open Discussion Regarding Materials for Nuclear ... Trends in Nuclear Power, The Nuclear Fuel Cycle, Nuclear Science...

53

Special Topics: Nuclear Materials  

Science Conference Proceedings (OSTI)

COURSE NOTES: Nuclear Science and Technology Part I/II (Chm466/566/ Phy446/546) W. Udo Schrder, University of Rochester. PPT, PDF, and audio lectures...

54

Nuclear Resonance Fluorescence for Materials Assay  

E-Print Network (OSTI)

screening of cargo for nuclear weapons materials [2],[3].peaceful nuclear activities are not diverted to weapons

Quiter, Brian J.

2010-01-01T23:59:59.000Z

55

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

National Nuclear Security Administration (NNSA)

Securing Domestic Radioactive Material | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency...

56

Nuclear Resonance Fluorescence for Nuclear Materials Assay  

E-Print Network (OSTI)

Potential of Nuclear Resonance Fluorescence . . . . . . . .2.9.1 Nuclear ThomsonSections . . . . . . . . . . . . . . . Nuclear Resonance

Quiter, Brian Joseph

2010-01-01T23:59:59.000Z

57

Nuclear Resonance Fluorescence for Materials Assay  

E-Print Network (OSTI)

clandestine material with nuclear resonance fluorescence.E. Norman, UC Berkeley Dept. of Nuclear Engineering, privatepp. 349. G. Warren et al. Nuclear Resonance Fluorescence of

Quiter, Brian

2010-01-01T23:59:59.000Z

58

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

National Nuclear Security Administration (NNSA)

Feb 1, 2011 The Department of Energy's National Nuclear Security Administration (NNSA), which has unique expertise in nuclear weapons and nuclear material, plays a key role in the...

59

Transportation of Nuclear Materials | Department of Energy  

NLE Websites -- All DOE Office Websites (Extended Search)

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...

60

WEB RESOURCE: TMS Nuclear Materials Committee  

Science Conference Proceedings (OSTI)

Feb 19, 2007 ... The mission of the TMS Nuclear Materials Committee encompasses the ... of nuclear energy technology and related areas of materials science...

Note: This page contains sample records for the topic "nuclear material control" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


61

Nuclear reactor control apparatus  

DOE Patents (OSTI)

Nuclear reactor core safety rod release apparatus comprises a control rod having a detent notch in the form of an annular peripheral recess at its upper end, a control rod support tube for raising and lowering the control rod under normal conditions, latches pivotally mounted on the control support tube with free ends thereof normally disposed in the recess in the control rod, and cam means for pivoting the latches out of the recess in the control rod when a scram condition occurs. One embodiment of the invention comprises an additional magnetically-operated latch for releasing the control rod under two different conditions, one involving seismic shock.

Sridhar, Bettadapur N. (Cupertino, CA)

1983-11-01T23:59:59.000Z

62

Nuclear Materials Disposition | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Materials Disposition Nuclear Materials Disposition Nuclear Materials Disposition Nuclear Materials Disposition 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 national security or other purposes, including spent nuclear fuel, special nuclear materials (as defined by the Atomic Energy Act) and other Nuclear Materials. Spent Nuclear Fuel Spent nuclear fuel (SNF) is fuel that has been withdrawn from a nuclear reactor following irradiation, the constituent elements of which have not been separated by reprocessing. SNF may include: (1) intact, non-defective fuel assemblies or fuel rods; (2) failed fuel assemblies or fuel rods; (3) segments of fuel rods or pieces of fuel derived from spent fuel rods; and

63

Materials Solutions for the Nuclear Renaissance  

Science Conference Proceedings (OSTI)

Nuclear reactors present a complex, challenging environment where innovations in materials ... Materials design for fast burner reactors and fusion research

64

Security of Nuclear Reactors and Special Nuclear Materials This revisiono  

E-Print Network (OSTI)

Provides requirements for the recovery of lost, seized, or stolen special nuclear material (para 2-1b). o Prescribes that unclassified information pertaining to plans, procedures, and equipment for the physical protection of nuclear reactors and special nuclear material will be safeguarded as DoD Unclassified Controlled Nuclear Information (para 2-1f). o Requires the conduct of a vulnerability assessment at each facility where special nuclear material is used or stored (para 2-2a). o Provides that Headquarters, U. S. Army Materiel Command will develop the postulated threat as the basis for the vulnerability assessment (para 2-2b), as well as the standardized format for documenting the results of the assessment and for the after action reports (para 2-2h). o Designates special nuclear material as inherently dangerous to others for use of force purposes (para 2-4a). o Prescribes minimum storage standards for special nuclear material (para 3-1). o Provides for the protection of vital equipment (para 3-3). o Explains the concept of the required security system for nuclear reactors and special nuclear material (para 4-2). o Establishes specific physical security standards for the protection of nuclear reactors and special nuclear material (para 4-4), to include required access controls (para 4-5). o Prohibits the locksmith from being designated as the key control officer or lock custodian (para 4-5g(25)). o Provides guidance on meeting requirement to continuously man two alarm monitoring facilities (para 4-6b). o Allows continued use of monitoring console systems installed prior to publication of this regulation that do not meet the map or video display requirement (para 4-6g(1)). o Provides guidance for testing the perimeter intrusion detection system (para 4-6n(2)). o Requires appropriate security personnel be trained to manually start the standby generator if the automatic starter fails to function properly (para 4-9b(4)). o Provides that the size, composition, and response time of the response force will be set by the major subordinate commander and approved by the Commanding

unknown authors

1993-01-01T23:59:59.000Z

65

Materials Challenges in Nuclear Energy  

SciTech Connect

Nuclear power currently provides about 13% of the worldwide electrical power, and has emerged as a reliable baseload source of electricity. A number of materials challenges must be successfully resolved for nuclear energy to continue to make further improvements in reliability, safety and economics. The operating environment for materials in current and proposed future nuclear energy systems is summarized, along with a description of materials used for the main operating components. Materials challenges associated with power uprates and extensions of the operating lifetimes of reactors are described. The three major materials challenges for the current and next generation of water-cooled fission reactors are centered on two structural materials aging degradation issues (corrosion and stress corrosion cracking of structural materials and neutron-induced embrittlement of reactor pressure vessels), along with improved fuel system reliability and accident tolerance issues. The major corrosion and stress corrosion cracking degradation mechanisms for light water reactors are reviewed. The materials degradation issues for the Zr alloy clad UO2 fuel system currently utilized in the majority of commercial nuclear power plants is discussed for normal and off-normal operating conditions. Looking to proposed future (Generation IV) fission and fusion energy systems, there are 5 key bulk radiation degradation effects (low temperature radiation hardening and embrittlement, radiation-induced and modified solute segregation and phase stability, irradiation creep, void swelling, and high temperature helium embrittlement) and a multitude of corrosion and stress corrosion cracking effects (including irradiation-assisted phenomena) that can have a major impact on the performance of structural materials.

Zinkle, Steven J [ORNL; Was, Gary [University of Michigan

2013-01-01T23:59:59.000Z

66

Nuclear and hazardous material perspective  

SciTech Connect

The reemerging nuclear enterprise in the 21. century empowering the power industry and nuclear technology is still viewed with fear and concern by many of the public and many political leaders. Nuclear phobia is also exhibited by many nuclear professionals. The fears and concerns of these groups are complex and varied, but focus primarily on (1) management and disposal of radioactive waste [especially spent nuclear fuel and low level radioactive waste], (2) radiation exposures at any level, and (3) the threat nuclear terrorism. The root cause of all these concerns is the exaggerated risk perceived to human health from radiation exposure. These risks from radiation exposure are compounded by the universal threat of nuclear weapons and the disastrous consequences if these weapons or materials become available to terrorists or rogue nations. This paper addresses the bases and rationality for these fears and considers methods and options for mitigating these fears. Scientific evidence and actual data are provided. Radiation risks are compared to similar risks from common chemicals and familiar human activities that are routinely accepted. (authors)

Sandquist, Gary M. [Applied Science Professionals, PO Box 9052 Salt Lake City, UT 84109 (United States); Kunze, Jay F. [Idaho State University PO Box 8060 Pocatello, ID 83209 (United States); Rogers, Vern C. [University of Utah PO Box 510087 Salt Lake City, UT 84151 (United States)

2007-07-01T23:59:59.000Z

67

Nuclear Resonance Fluorescence for Nuclear Materials Assay  

E-Print Network (OSTI)

Energy Transmission say for Nuclear Fuel Assemblies 4.1Facilities Spent nuclear fuel is another example wherein intact spent nuclear fuel would be a technological

Quiter, Brian Joseph

2010-01-01T23:59:59.000Z

68

Nuclear Resonance Fluorescence for Nuclear Materials Assay  

E-Print Network (OSTI)

and Diablo Canyon 2 nuclear reactors. Data were taken fromCapacity Operation of nuclear reactors for power generationby the operation of nuclear reactors. Therefore, ap-

Quiter, Brian Joseph

2010-01-01T23:59:59.000Z

69

Nuclear Resonance Fluorescence for Nuclear Materials Assay  

E-Print Network (OSTI)

that are of interest for nuclear security applications. Theof interest to nuclear security. To either make theseother targets of nuclear security interest, such kilogram-

Quiter, Brian Joseph

2010-01-01T23:59:59.000Z

70

Recommendations to the NRC on acceptable standard format and content for the Fundamental Nuclear Material Control (FNMC) Plan required for low-enriched uranium enrichment facilities  

SciTech Connect

A new section, 10 CFR 74.33, has been added to the material control and accounting (MC A) requirements of 10 CFR Part 74. This new section pertains to US Nuclear Regulatory Commission (NRC)-licensed uranium enrichment facilities that are authorized to produce and to possess more than one effective kilogram of special nuclear material (SNM) of low strategic significance. The new section is patterned after 10 CFR 74.31, which pertains to NRC licensees (other than production or utilization facilities licensed pursuant to 10 CFR Part 50 and 70 and waste disposal facilities) that are authorized to possess and use more than one effective kilogram of unencapsulated SNM of low strategic significance. Because enrichment facilities have the potential capability of producing SNM of moderate strategic significance and also strategic SNM, certain performance objectives and MC A system capabilities are required in 10 CFR 74.33 that are not contained in 10 CFR 74.31. This document recommends to the NRC information that the licensee or applicant should provide in the fundamental nuclear material control (FNMC) plan. This document also describes methods that should be acceptable for compliance with the general performance objectives. While this document is intended to cover various uranium enrichment technologies, the primary focus at this time is gas centrifuge and gaseous diffusion.

Moran, B.W.; Belew, W.L. (Oak Ridge K-25 Site, TN (United States)); Hammond, G.A.; Brenner, L.M. (21st Century Industries, Inc., Gaithersburg, MD (United States))

1991-11-01T23:59:59.000Z

71

Materials for Nuclear Power: Digital Resource Center ...  

Science Conference Proceedings (OSTI)

Agency regulating commercial nuclear power plants and other uses of nuclear materials, 0, 720, Lynne Robinson, 6/25/2007 9:29 AM by Lynne Robinson.

72

Nuclear reactor control  

DOE Patents (OSTI)

1. In a nuclear reactor incorporating a plurality of columns of tubular fuel elements disposed in horizontal tubes in a mass of graphite wherein water flows through the tubes to cool the fuel elements, the improvement comprising at least one control column disposed in a horizontal tube including fewer fuel elements than in a normal column of fuel elements and tubular control elements disposed at both ends of said control column, and means for varying the horizontal displacement of the control column comprising a winch at the upstream end of the control column and a cable extending through the fuel and control elements and attached to the element at the downstream end of the column.

Cawley, William E. (Phoenix, AZ); Warnick, Robert F. (Pasco, WA)

1982-01-01T23:59:59.000Z

73

NUCLEAR REACTOR COMPENENT CLADDING MATERIAL  

DOE Patents (OSTI)

Fuel elements and coolant tubes used in nuclear reactors of the heterogeneous, water-cooled type are described, wherein the coolant tubes extend through the moderator and are adapted to contain the fuel elements. The invention comprises forming the coolant tubes and the fuel element cladding material from an alloy of aluminum and nickel, or an alloy of aluminum, nickel, alloys are selected to prevent intergranular corrosion of these components by water at temperatures up to 35O deg C.

Draley, J.E.; Ruther, W.E.

1959-01-27T23:59:59.000Z

74

Nuclear reactor control column  

DOE Patents (OSTI)

The nuclear reactor control column comprises a column disposed within the nuclear reactor core having a variable cross-section hollow channel and containing balls whose vertical location is determined by the flow of the reactor coolant through the column. The control column is divided into three basic sections wherein each of the sections has a different cross-sectional area. The uppermost section of the control column has the greatest cross-sectional area, the intermediate section of the control column has the smallest cross-sectional area, and the lowermost section of the control column has the intermediate cross-sectional area. In this manner, the area of the uppermost section can be established such that when the reactor coolant is flowing under normal conditions therethrough, the absorber balls will be lifted and suspended in a fluidized bed manner in the upper section. However, when the reactor coolant flow falls below a predetermined value, the absorber balls will fall through the intermediate section and into the lowermost section, thereby reducing the reactivity of the reactor core and shutting down the reactor.

Bachovchin, Dennis M. (Plum Borough, PA)

1982-01-01T23:59:59.000Z

75

Structural Materials in Advanced Nuclear Energy Systems  

Science Conference Proceedings (OSTI)

Apr 28, 2008 ... Structural Materials in Advanced Nuclear Energy Systems: The Need for ... of functionalized interfaces for optimization of materials properties.

76

Materials for Nuclear Power: Digital Resource Center ...  

Science Conference Proceedings (OSTI)

PRESENTATONS: Reawakening of United States Nuclear Energy: Materials Challenges for a New Generation of Power Plants Presentations by Harold...

77

WEB RESOURCE: Nuclear Engineering Materials - TMS  

Science Conference Proceedings (OSTI)

Feb 12, 2007 ... "Nuclear Engineering Materials." Engineering Physics Department, College of Engineering. University of Wisconsin-Madison, Fall 2006.

78

Accelerated Materials Evaluation for Nuclear Application Utilizing ...  

Science Conference Proceedings (OSTI)

Jul 15, 2013... of accelerated nuclear materials testing for fission and fusion reactors. Presentations combining experiment with theory, modeling and...

79

Interim Management of Nuclear Materials  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

1995/01_eis0220_for.html[6/27/2011 12:53:53 PM] 1995/01_eis0220_for.html[6/27/2011 12:53:53 PM] FOREWORD The Savannah River Site (SRS) is a major Department of Energy (DOE) installation. The past mission of the SRS was to produce nuclear materials that supported the defense, research, and medical programs of the United States. In 1992 the Secretary of Energy directed the SRS to phase out defense-related chemical separations activities. As a result of shutdowns and reduced demand for nuclear materials, the SRS presently has a large inventory of in-process solutions, reactor fuel assemblies, and reactor targets. These materials, due to their form or to the condition in which they are maintained, could represent a concern for the public, worker health and safety, and the environment. DOE published a Notice of Intent (NOI) to prepare this environmental impact statement (EIS) on March 17, 1994 (59

80

Interim Management of Nuclear Materials  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

1995/01_eis0220_for.html[6/27/2011 12:53:53 PM] 1995/01_eis0220_for.html[6/27/2011 12:53:53 PM] FOREWORD The Savannah River Site (SRS) is a major Department of Energy (DOE) installation. The past mission of the SRS was to produce nuclear materials that supported the defense, research, and medical programs of the United States. In 1992 the Secretary of Energy directed the SRS to phase out defense-related chemical separations activities. As a result of shutdowns and reduced demand for nuclear materials, the SRS presently has a large inventory of in-process solutions, reactor fuel assemblies, and reactor targets. These materials, due to their form or to the condition in which they are maintained, could represent a concern for the public, worker health and safety, and the environment. DOE published a Notice of Intent (NOI) to prepare this environmental impact statement (EIS) on March 17, 1994 (59

Note: This page contains sample records for the topic "nuclear material control" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


81

Fieldable Nuclear Material Identification System  

SciTech Connect

The Fieldable Nuclear Material Identification System (FNMIS), funded by the NA-241 Office of Dismantlement and Transparency, provides information to determine the material attributes and identity of heavily shielded nuclear objects. This information will provide future treaty participants with verifiable information required by the treaty regime. The neutron interrogation technology uses a combination of information from induced fission neutron radiation and transmitted neutron imaging information to provide high confidence that the shielded item is consistent with the host's declaration. The combination of material identification information and the shape and configuration of the item are very difficult to spoof. When used at various points in the warhead dismantlement sequence, the information complimented by tags and seals can be used to track subassembly and piece part information as the disassembly occurs. The neutron transmission imaging has been developed during the last seven years and the signature analysis over the last several decades. The FNMIS is the culmination of the effort to put the technology in a usable configuration for potential treaty verification purposes.

Radle, James E [ORNL; Archer, Daniel E [ORNL; Carter, Robert J [ORNL; Mullens, James Allen [ORNL; Mihalczo, John T [ORNL; Britton Jr, Charles L [ORNL; Lind, Randall F [ORNL; Wright, Michael C [ORNL

2010-01-01T23:59:59.000Z

82

GTRI's Nuclear and Radiological Material Protection | National Nuclear  

NLE Websites -- All DOE Office Websites (Extended Search)

Protection | National Nuclear Protection | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog GTRI's Nuclear and Radiological Material Protection Home > About Us > Our Programs > Nonproliferation > Global Threat Reduction Initiative > GTRI's Nuclear and Radiological Material Protection GTRI's Nuclear and Radiological Material Protection

83

Insider Threat - Material Control and Accountability Mitigation  

Science Conference Proceedings (OSTI)

The technical objectives of nuclear safeguards are (1) the timely detection of diversion of significant quantities of nuclear material from peaceful uses to the manufacture of nuclear weapons or other nuclear explosive devices or for purposes unknown and (2) the deterrence of such diversion by the risk of early detection. The safeguards and security program must address both outsider threats and insider threats. Outsider threats are primarily addressed by the physical protection system. Insider threats can be any level of personnel at the site including passive or active insiders that could attempt protracted or abrupt diversion. This could occur by an individual acting alone or by collusion between an individual with material control and accountability (MC&A) responsibilities and another individual who has responsibility or control within both the physical protection and the MC&A systems. The insider threat is one that must be understood and incorporated into the safeguards posture. There have been more than 18 documented cases of theft or loss of plutonium or highly enriched uranium. The insider has access, authority, and knowledge, as well as a set of attributes, that make him/her difficult to detect. An integrated safeguards program is designed as a defense-in-depth system that seeks to prevent the unauthorized removal of nuclear material, to provide early detection of any unauthorized attempt to remove nuclear material, and to rapidly respond to any attempted removal of nuclear material. The program is also designed to support protection against sabotage, espionage, unauthorized access, compromise, and other hostile acts that may cause unacceptable adverse impacts on national security, program continuity, the health and safety of employees, the public, or the environment. Nuclear MC&A play an essential role in the capabilities of an integrated safeguards system to deter and detect theft or diversion of nuclear material. An integrated safeguards system with compensating mitigation can decrease the risk of an insider performing a malicious act without detection.

Powell, Danny H [ORNL; Elwood Jr, Robert H [ORNL; Roche, Charles T [ORNL

2011-01-01T23:59:59.000Z

84

Nuclear and Radiological Material Security | National Nuclear...  

National Nuclear Security Administration (NNSA)

to intensive site security efforts, NNSA is also working to build international standards and criteria for nuclear and radiological security. This includes NNSA's work to...

85

Fissile Materials Disposition | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Fissile Materials Disposition | National Nuclear Security Administration Fissile Materials Disposition | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Fissile Materials Disposition Home > About Us > Our Programs > Nonproliferation > Fissile Materials Disposition Fissile Materials Disposition Since the end of the Cold War, significant quantities of plutonium and

86

International Materials Protection and Cooperation | National Nuclear  

National Nuclear Security Administration (NNSA)

Materials Protection and Cooperation | National Nuclear Materials Protection and Cooperation | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog International Materials Protection and Cooperation Home > About Us > Our Programs > Nonproliferation > International Materials Protection and Cooperation International Materials Protection and Cooperation

87

FINAL (PNNL-20432) Nuclear Nonproliferation and Arms Control Primer  

E-Print Network (OSTI)

.g., North Korea, Pakistan). Fissile materials, nuclear reactors, reprocessing and enrichment technologyFINAL (PNNL-20432) 1 Nuclear Nonproliferation and Arms Control Primer Prepared for the Blue Ribbon Commission on America's Nuclear Future Although the list of U.S. nuclear nonproliferation and arms control

88

Materials Development and Degradation Management for Nuclear ...  

Science Conference Proceedings (OSTI)

Materials Development and Degradation Management for Nuclear ... of zirconium alloys in reactor can lead to the presence of hydride precipitates, and can ... for the U.S. Department ofEnergy's National Nuclear Security Administration under...

89

Techniques and methods in nuclear materials traceability  

SciTech Connect

The nonproliferation community is currently addressing concerns that the access to special nuclear materials may increase the illicit trafficking in weapons-usable materials from civil and/or weapons material stores and/or fuel cycles systems. Illicit nuclear traffic usually involves reduced quantities of nuclear materials perhaps as samplings of a potential protracted diversionary flow from sources to users. To counter illicit nuclear transactions requires the development of techniques and methods in nuclear material traceability as an important phase of a broad forensic analysis capability. This report discusses how isotopic signatures and correlation methods were applied to determine the origins of Highly Enriched Uranium (HEU) and Plutonium samples reported as illicit trafficking in nuclear materials.

Persiani, P.J.

1996-08-01T23:59:59.000Z

90

Nuclear and Radiological Material Security | National Nuclear...  

National Nuclear Security Administration (NNSA)

17, 2013 NNSA, Republic of Korea Ministry Agree to Minimize Use of HEU in Nuclear Reactors Sep 3, 2013 NNSA Conducts Two Emergency Response Training Courses in Armenia Aug 29, 2013...

91

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

National Nuclear Security Administration (NNSA)

17, 2013 NNSA, Republic of Korea Ministry Agree to Minimize Use of HEU in Nuclear Reactors Sep 3, 2013 NNSA Conducts Two Emergency Response Training Courses in Armenia Aug 29, 2013...

92

SRS - Programs - H Area Nuclear Materials Disposition  

NLE Websites -- All DOE Office Websites (Extended Search)

H Area Nuclear Materials Disposition H Area Nuclear Materials Disposition The primary mission of the H-Canyon Complex is to dissolve, purify and blend-down surplus highly enriched uranium (HEU) and aluminum-clad foreign and domestic research reactor fuel to produce a low enriched uranium (LEU) solution suitable for conversion to commercial reactor fuel. A secondary mission for H-Canyon is to dissolve excess plutonium (Pu) not suitable for MOX and transfer it for vitrification in the Defense Waste Processing Facility at SRS. H Canyon was constructed in the early 1950s and began operations in 1955. The building is called a canyon because of its long rectangular shape and two continuous trenches that contains the process vessels. It is approximately 1,000 feet long with several levels to accommodate the various stages of material stabilization, including control rooms to monitor overall equipment and operating processes, equipment and piping gallery for solution transport, storage, and disposition, and unique overhead bridge cranes to support overall process operations. All work is remotely controlled, and employees are further protected from radiation by thick concrete walls.

93

Nuclear Materials Management & Safeguards System CONTACT INFORMATION...  

National Nuclear Security Administration (NNSA)

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

94

Materials in Nuclear Power Plant Construction - TMS  

Science Conference Proceedings (OSTI)

139th Annual Meeting & Exhibition. February 14 - 18, 2010, Washington State Convention Center, Seattle, Washington USA. Materials in Nuclear Power. Plant ...

95

COURSE NOTES: Nuclear Engineering Materials (NEEP 423)  

Science Conference Proceedings (OSTI)

Jul 2, 2008 ... "Nuclear Engineering Materials (NEEP 423)." Department of Engineering Physics . Fall 2006. University of Wisconsin-Madison. Launch Site

96

COURSE NOTES: Nuclear Materials (NE120)  

Science Conference Proceedings (OSTI)

Feb 10, 2007 ... This resource provides PDF lecture notes and readings for an undergraduate course covering materials issues in nuclear power systems.

97

Materials Science of Nuclear Waste Management  

Science Conference Proceedings (OSTI)

The intent is to provide a forum for researchers from national laboratories, universities, and nuclear industry to discuss current understanding of materials...

98

Materials for Nuclear Power A Brief Introduction  

Science Conference Proceedings (OSTI)

Feb 10, 2007 ... A brief introduction to the effects of irradiation on materials for the nuclear power industry. PDF article includes figures and useful links.

99

Materials for Nuclear Power: Digital Resource Center ...  

Science Conference Proceedings (OSTI)

May 25, 2007 ... The United States Nuclear Power Industry is reawakening. ... for a New Generation of Power Plants", Materials Technology@TMS, May 2007.

100

Advanced research workshop: nuclear materials safety  

SciTech Connect

The Advanced Research Workshop (ARW) on Nuclear Materials Safety held June 8-10, 1998, in St. Petersburg, Russia, was attended by 27 Russian experts from 14 different Russian organizations, seven European experts from six different organizations, and 14 U.S. experts from seven different organizations. The ARW was conducted at the State Education Center (SEC), a former Minatom nuclear training center in St. Petersburg. Thirty-three technical presentations were made using simultaneous translations. These presentations are reprinted in this volume as a formal ARW Proceedings in the NATO Science Series. The representative technical papers contained here cover nuclear material safety topics on the storage and disposition of excess plutonium and high enriched uranium (HEU) fissile materials, including vitrification, mixed oxide (MOX) fuel fabrication, plutonium ceramics, reprocessing, geologic disposal, transportation, and Russian regulatory processes. This ARW completed discussions by experts of the nuclear materials safety topics that were not covered in the previous, companion ARW on Nuclear Materials Safety held in Amarillo, Texas, in March 1997. These two workshops, when viewed together as a set, have addressed most nuclear material aspects of the storage and disposition operations required for excess HEU and plutonium. As a result, specific experts in nuclear materials safety have been identified, know each other from their participation in t he two ARW interactions, and have developed a partial consensus and dialogue on the most urgent nuclear materials safety topics to be addressed in a formal bilateral program on t he subject. A strong basis now exists for maintaining and developing a continuing dialogue between Russian, European, and U.S. experts in nuclear materials safety that will improve the safety of future nuclear materials operations in all the countries involved because of t he positive synergistic effects of focusing these diverse backgrounds of nuclear experience on a common objectivethe safe and secure storage and disposition of excess fissile nuclear materials.

Jardine, L J; Moshkov, M M

1999-01-28T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear material control" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

Industry Survey of Radioactive Material Control Practices  

Science Conference Proceedings (OSTI)

Workers and materials entering and exiting the radiation control areas (RCAs) of nuclear power plants are carefully monitored for radioactivity. This report documents a survey developed to evaluate the range of instrumentation and practices used by the industry for performing such measurements.

2003-11-26T23:59:59.000Z

102

Nuclear Resonance Fluorescence for Nuclear Materials Assay  

E-Print Network (OSTI)

purposes. Presently, uranium enrichments are measured by oneweapons annually. Enrichment of uranium is necessary to makeof uranium isotopes in materials at enrichment facilities is

Quiter, Brian Joseph

2010-01-01T23:59:59.000Z

103

Regulatory Guide 5.29, Revision 2, "Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants".  

National Nuclear Security Administration (NNSA)

U.S. NUCLEAR REGULATORY COMMISSION June 2013 U.S. 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 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/. The regulatory guide is also available through the NRC's Agencywide Documents Access and Management System (ADAMS) at

104

Materials for Nuclear Power: Digital Resource Center - WEBCAST ...  

Science Conference Proceedings (OSTI)

May 25, 2007 ... Select, Sandbox, Open Discussion Regarding Materials for Nuclear ... Trends in Nuclear Power, The Nuclear Fuel Cycle, Nuclear Science...

105

Materials for Nuclear Power: Digital Resource Center - WEB ...  

Science Conference Proceedings (OSTI)

Feb 12, 2007 ... Select, Sandbox, Open Discussion Regarding Materials for Nuclear ... Trends in Nuclear Power, The Nuclear Fuel Cycle, Nuclear Science...

106

Materials for Nuclear Power: Digital Resource Center - JOM Article ...  

Science Conference Proceedings (OSTI)

Mar 15, 2009 ... Select, Sandbox, Open Discussion Regarding Materials for Nuclear ... Trends in Nuclear Power, The Nuclear Fuel Cycle, Nuclear Science...

107

Materials for Nuclear Power: Digital Resource Center - BOOK ...  

Science Conference Proceedings (OSTI)

Feb 12, 2007 ... Select, Sandbox, Open Discussion Regarding Materials for Nuclear ... Trends in Nuclear Power, The Nuclear Fuel Cycle, Nuclear Science...

108

Materials for Nuclear Power: Digital Resource Center - What long ...  

Science Conference Proceedings (OSTI)

Jan 4, 2008 ... Select, Sandbox, Open Discussion Regarding Materials for Nuclear ... Trends in Nuclear Power, The Nuclear Fuel Cycle, Nuclear Science...

109

A REPRINT of a July 1991 Report to Congress, Executive Summary of Verification of Nuclear Warhead Dismantlement and Special Nuclear Material Controls  

Science Conference Proceedings (OSTI)

With the renewed thinking and debate about deep reductions in nuclear weapons, including recent proposals about eliminating nuclear warheads altogether, republishing the general conclusions of the Robinson Committee Report of 1992 appears useful. The report is sometimes referred to as the 3151 Report, from Section 3151 of the National Defnse Authorization Act for FY1991, from where its requirement originated. This report contains the Executive Summary only and the forwarding letters from the Committee, the President of the United States, the Secretary of Energy, and C Paul Robinson, the head of the Advisory Committee.

Fuller, James L.

2008-11-20T23:59:59.000Z

110

Metabonomics for detection of nuclear materials processing.  

SciTech Connect

Tracking nuclear materials production and processing, particularly covert operations, is a key national security concern, given that nuclear materials processing can be a signature of nuclear weapons activities by US adversaries. Covert trafficking can also result in homeland security threats, most notably allowing terrorists to assemble devices such as dirty bombs. Existing methods depend on isotope analysis and do not necessarily detect chronic low-level exposure. In this project, indigenous organisms such as plants, small mammals, and bacteria are utilized as living sensors for the presence of chemicals used in nuclear materials processing. Such 'metabolic fingerprinting' (or 'metabonomics') employs nuclear magnetic resonance (NMR) spectroscopy to assess alterations in organismal metabolism provoked by the environmental presence of nuclear materials processing, for example the tributyl phosphate employed in the processing of spent reactor fuel rods to extract and purify uranium and plutonium for weaponization.

Alam, Todd Michael; Luxon, Bruce A. (University Texas Medical Branch); Neerathilingam, Muniasamy (University Texas Medical Branch); Ansari, S. (University Texas Medical Branch); Volk, David (University Texas Medical Branch); Sarkar, S. (University Texas Medical Branch); Alam, Mary Kathleen

2010-08-01T23:59:59.000Z

111

Nuclear Forensic Reference Materials (RM) for Attribution of ...  

Science Conference Proceedings (OSTI)

... Nuclear Materials Fuel cycles Limit fissile material production Reactor conversion Securing SNM Reliable inventories Physical Security ...

2012-12-06T23:59:59.000Z

112

Materials for Nuclear Power: Digital Resource Center - WEB ...  

Science Conference Proceedings (OSTI)

May 7, 2007 ... Select, Sandbox, Open Discussion Regarding Materials for Nuclear Power ... Trends in Nuclear Power, The Nuclear Fuel Cycle, Nuclear Science, Nuclear ... This 'thermodynamic database for advanced nuclear fuels' was...

113

UNCLASSIFIED Nuclear Materials Management & Safeguards System  

National Nuclear Security Administration (NNSA)

Nuclear Materials Management & Safeguards System 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.

114

Nuclear Materials Science:Materials Science Technology:MST-16...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Materials Science (MST-16) Home About Us MST Related Links Research Highlights Focus on Facilities MST e-News Experimental Physical Sciences Vistas MaRIE: Matter-Radiation...

115

Nuclear Concrete Materials Database Phase I Development  

Science Conference Proceedings (OSTI)

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.

Ren, Weiju [ORNL; Naus, Dan J [ORNL

2012-05-01T23:59:59.000Z

116

Reactivity control assembly for nuclear reactor. [LMFBR  

DOE Patents (OSTI)

This invention, which resulted from a contact with the United States Department of Energy, relates to a control mechanism for a nuclear reactor and, more particularly, to an assembly for selectively shifting different numbers of reactivity modifying rods into and out of the core of a nuclear reactor. It has been proposed heretofore to control the reactivity of a breeder reactor by varying the depth of insertion of control rods (e.g., rods containing a fertile material such as ThO/sub 2/) in the core of the reactor, thereby varying the amount of neutron-thermalizing coolant and the amount of neutron-capturing material in the core. This invention relates to a mechanism which can advantageously be used in this type of reactor control system.

Bollinger, L.R.

1982-03-17T23:59:59.000Z

117

Special Topics: Nuclear Materials: Books/Articles  

Science Conference Proceedings (OSTI)

PDF article introducing the effects of irradiation on materials for the nuclear power industry, 0, 588, Cathy Rohrer, 2/10/2007 5:16 PM by Cathy Rohrer. FORUMS...

118

Office of Fissile Materials Disposition | National Nuclear Security...  

NLE Websites -- All DOE Office Websites (Extended Search)

Fissile Materials Disposition | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

119

Interim Management of Nuclear Materials  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Summary-1995.html[6/27/2011 12:50:20 PM] Summary-1995.html[6/27/2011 12:50:20 PM] SUMMARY The Atomic Energy Commission (AEC), a predecessor agency of the Department of Energy (DOE), established the Savannah River Site (SRS) in the early 1950s for the production of special radioactive isotopes. The primary SRS mission was to produce strategic isotopes (plutonium-239 and tritium) used in the development and production of nuclear weapons for national defense. The Site produced other special isotopes (californium-252, plutonium-238, americium-241, etc.) to support research in nuclear medicine, space exploration, and commercial applications. The historic production cycle at the SRS involved the fabrication of metal fuel and target assemblies for irradiation in the Site reactors, followed by chemical dissolution, separation, and conversion of the radioisotopes into solid forms for use

120

Materials for Nuclear Power: Digital Resource Center - WEB ... - TMS  

Science Conference Proceedings (OSTI)

Jun 25, 2007 ... The NRC regulates commercial nuclear power plants and other uses of nuclear materials, such as in nuclear medicine, through licensing,...

Note: This page contains sample records for the topic "nuclear material control" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

Nuclear Controls | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

122

Potential applications of nanostructured materials in nuclear waste management.  

Science Conference Proceedings (OSTI)

This report summarizes the results obtained from a Laboratory Directed Research & Development (LDRD) project entitled 'Investigation of Potential Applications of Self-Assembled Nanostructured Materials in Nuclear Waste Management'. The objectives of this project are to (1) provide a mechanistic understanding of the control of nanometer-scale structures on the ion sorption capability of materials and (2) develop appropriate engineering approaches to improving material properties based on such an understanding.

Braterman, Paul S. (The University of North Texas, Denton, TX); Phol, Phillip Isabio; Xu, Zhi-Ping (The University of North Texas, Denton, TX); Brinker, C. Jeffrey; Yang, Yi (University of New Mexico, Albuquerque, NM); Bryan, Charles R.; Yu, Kui; Xu, Huifang (University of New Mexico, Albuquerque, NM); Wang, Yifeng; Gao, Huizhen

2003-09-01T23:59:59.000Z

123

International safeguards: Accounting for nuclear materials  

SciTech Connect

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.

Fishbone, L.G.

1988-09-28T23:59:59.000Z

124

Nuclear reactor control apparatus  

DOE Patents (OSTI)

Nuclear reactor safety rod release apparatus comprises a ring which carries detents normally positioned in an annular recess in outer side of the rod, the ring being held against the lower end of a drive shaft by magnetic force exerted by a solenoid carried by the drive shaft. When the solenoid is de-energized, the detent-carrying ring drops until the detents contact a cam surface associated with the lower end of the drive shaft, at which point the detents are cammed out of the recess in the safety rod to release the rod from the drive shaft. In preferred embodiments of the invention, an additional latch is provided to release a lower portion of a safety rod under conditions that may interfere with movement of the entire rod.

Sridhar, Bettadapur N. (Cupertino, CA)

1983-10-25T23:59:59.000Z

125

Introduction to Nuclear Reactors, Fuels, and Materials: Heather ...  

Science Conference Proceedings (OSTI)

Feb 27, 2012 ... What goes on in a nuclear power plant. Challenges in nuclear fuels and materials. Key lessons: Fuels and materials change during...

126

Nuclear Material Recovery | Y-12 National Security Complex  

NLE Websites -- All DOE Office Websites (Extended Search)

Recovery Securing nuclear material domestically and internationally is one part of Y-12's nuclear nonproliferation business. Miscellaneous scrap material is a diverse group of...

127

bylaws of the nuclear materials committee of the minerals, metals ...  

Science Conference Proceedings (OSTI)

The name of this technical committee shall be the Nuclear Materials. Committee ... aspects of materials, which are utilized in all areas of nuclear energy.

128

Nuclear Fuels and Materials: Jon Carmack, Idaho National Laboratory  

Science Conference Proceedings (OSTI)

Feb 28, 2012 ... w w w .in. l.g o v. Nuclear Fuels and Materials. Jon Carmack. Nuclear Fuels and Materials Division. Idaho National Laboratory. February 28...

129

Nuclear Power - Control, Reliability and Human Factors  

E-Print Network (OSTI)

Advances in reactor designs, materials and human-machine interfaces guarantee safety and reliability of emerging reactor technologies, eliminating possibilities for high-consequence human errors as those which have occurred in the past. New instrumentation and control technologies based in digital systems, novel sensors and measurement approaches facilitate safety, reliability and economic competitiveness of nuclear power options. Autonomous operation scenarios are becoming increasingly popular to consider for small modular systems. This book belongs to a series of books on nuclear power published by InTech. It consists of four major sections and contains twenty-one chapters on topics from key subject areas pertinent to instrumentation and control, operation reliability, system aging and human-machine interfaces. The book targets a broad potential readership group - students, researchers and specialists in the field - who are interested in learning about nuclear power.

Tsvetkov, Pavel

2011-09-01T23:59:59.000Z

130

Interface Affected Cascading In Nuclear Materials and Its Correlation ...  

Science Conference Proceedings (OSTI)

About this Abstract. Meeting, Materials Science & Technology 2012. Symposium, Materials Development for Nuclear Applications and Extreme Environments.

131

Nuclear reactor control room construction  

DOE Patents (OSTI)

A control room for a nuclear plant is disclosed. In the control room, objects labelled 12, 20, 22, 26, 30 in the drawing are no less than four inches from walls labelled 10.2. A ceiling contains cooling fins that extend downwards toward the floor from metal plates. A concrete slab is poured over the plates. Studs are welded to the plates and are encased in the concrete. 6 figures.

Lamuro, R.C.; Orr, R.

1993-11-16T23:59:59.000Z

132

Advanced nuclear plant control complex  

DOE Patents (OSTI)

An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

Scarola, Kenneth (Windsor, CT); Jamison, David S. (Windsor, CT); Manazir, Richard M. (North Canton, CT); Rescorl, Robert L. (Vernon, CT); Harmon, Daryl L. (Enfield, CT)

1993-01-01T23:59:59.000Z

133

A future vision of nuclear material information systems  

SciTech Connect

To address the current and future needs for nuclear materials management and safeguards information, Lawrence Livermore National Laboratory envisions an integrated nuclear information system that will support several functions. The vision is to link distributed information systems via a common communications infrastructure designed to address the information interdependencies between two major elements: Domestic, with information about specific nuclear materials and their properties, and International, with information pertaining to foreign nuclear materials, facility design and operations. The communication infrastructure will enable data consistency, validation and reconciliation, as well as provide a common access point and user interface for a broad range of nuclear materials information. Information may be transmitted to, from, and within the system by a variety of linkage mechanisms, including the Internet. Strict access control will be employed as well as data encryption and user authentication to provide the necessary information assurance. The system can provide a mechanism not only for data storage and retrieval, but will eventually provide the analytical tools necessary to support the U.S. government's nuclear materials management needs and non-proliferation policy goals.

Suski, N; Wimple, C

1999-07-18T23:59:59.000Z

134

Nuclear fuel elements made from nanophase materials  

DOE Patents (OSTI)

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 3,000 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.

Heubeck, Norman B.

1997-12-01T23:59:59.000Z

135

Nuclear fuel elements made from nanophase materials  

SciTech Connect

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.

Heubeck, Norman B. (Schenectady, NY)

1998-01-01T23:59:59.000Z

136

Nuclear fuel elements made from nanophase materials  

DOE Patents (OSTI)

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.

Heubeck, N.B.

1998-09-08T23:59:59.000Z

137

Materials Research Needs for Near-Term Nuclear Reactors  

Science Conference Proceedings (OSTI)

Technical Paper / NSF Workshop on the Research Needs of the Next Generation Nuclear Power Technology / Material

John R. Weeks

138

Climate Control Using Nuclear Energy  

E-Print Network (OSTI)

We examine implications of anthropogenic low pressure regions, - created by injecting heat from nuclear reactors, into atmosphere. We suggest the possibility that such artificially generated low pressure regions, near hurricanes could disrupt their growth, path, and intensity. This method can also create controlled tropical stroms, which lead to substantial rainfall in arid areas, such as - (1)Sahara desert, (2) Australian interior desert, and (3) Indian Thar desert. A simple vortex suction model is developed to study, effect on atmospheric dynamics, by such a nuclear heat injection system.

Moninder Singh Modgil

2008-01-01T23:59:59.000Z

139

Safeguards and Nuclear Materials Management: A view from the DOE Chicago Operations Office  

SciTech Connect

Nuclear Materials Safeguards (also known as Material Control and Accountability or MC&A) and Nuclear Materials Management as practiced within the US Department of Energy (DOE) are separate, but related disciplines with differing goals and objectives. Safeguards and Nuclear Materials Management are closely related through the common use of transaction and inventory reporting data from the Nuclear Materials Management and Safeguards System (NMMSS). Adherence to Nuclear Materials management principals may enhance Nuclear Materials Safeguards, and has the potential to result in savings for both program and safeguards costs. Both the Safeguards and Nuclear Materials Management Programs for the Chicago Operations Office are administered by the Safeguards and Security Division, Safeguards Branch. This paper discusses Safeguards and Materials Management issues within the Chicago Operations Office, some of which relate to problems faced by the DOE complex as a whole.

Healy, F.E.; Ahlberg, C.G.

1994-07-01T23:59:59.000Z

140

Engineering Fundamentals - Nuclear Power Plant Materials, Version 2.0  

Science Conference Proceedings (OSTI)

The Engineering Fundamentals - Nuclear Power Plant Materials (EF-Materials) Version 2.0 computer-based training module provides new-hire engineering personnel with an overview of the basic concepts of nuclear power plant materials. Graphics and interactive features are used to enhance learning.EF-Materials covers the basic terms and concepts related to nuclear power plant materials and provides information about the significance of material degradation issues in nuclear power plants. ...

2012-11-30T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear material control" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

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

SciTech Connect

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.

Michael Holzemer; Alan Carvo

2012-04-01T23:59:59.000Z

142

Integrated Global Nuclear Materials Management - Preliminary Concepts -  

SciTech Connect

Approach to Connect Global Objectives and Local Actions: (1) Articulate global objectives into a hierarchy of subsystem requirements and local attributes and measures; (2) Establish a baseline system and viable alternatives through the interactions and relationships (e.g., networks) of local system elements and their options; (3) Evaluate performance of system alternatives and develop improved nuclear material management strategies and technologies; and (4) The need to address greatest concerns first (prioritized or graded approach) and to make tradeoffs among implementation options and competing objectives entails a risk-based approach. IGNMM could provide a systematic understanding of global nuclear materials management and evolutionarily improve and integrate the management through an active architecture, using for example, situation awareness, system models, methods, technologies, and international cooperation. Different tools would be used within the overall framework to address individual issues on the desired geographic scale that could be easily linked to broader analyses. Life-cycle system analyses would allow for evaluating material path alternatives on an integrated global scale. Disconnects, overlaps, technical options, and alternatives for optimizing nuclear materials processes could be evaluated in an integrated manner.

Dreicer, M; Jones, E; Richardson, J

2006-07-13T23:59:59.000Z

143

Materials for Nuclear Power: Digital Resource Center ... - TMS  

Science Conference Proceedings (OSTI)

Materials for Nuclear Power, 0, 2175, Maureen Byko, 3/15/2009 8:21 PM ... A comprehensive introductory educational site about all forms of nuclear power, 0...

144

Materials Physics and Applications Division Lead | National Nuclear...  

National Nuclear Security Administration (NNSA)

Materials Physics and Applications Division Lead | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy...

145

Insider Threat to Nuclear and Radiological Materials: Fact Sheet...  

NLE Websites -- All DOE Office Websites (Extended Search)

Insider Threat to Nuclear and Radiological Materials: Fact Sheet | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the...

146

Materials for Nuclear Power: Digital Resource Center ... - TMS  

Science Conference Proceedings (OSTI)

Materials for Nuclear Power, 0, 2161, Maureen Byko, 3/15/2009 8:21 PM ... A comprehensive introductory educational site about all forms of nuclear power, 0...

147

Materials for Nuclear Power: Digital Resource Center - ARTICLES ...  

Science Conference Proceedings (OSTI)

Jan 4, 2008 ... The January 2008 JOM offers the following articles covering disposition of nuclear waste: Material Corrosion Issues for Nuclear Waste...

148

Microsoft Word - Final Nuclear Materials Management and Safeguards...  

National Nuclear Security Administration (NNSA)

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

149

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

Office of Science (SC) Website

Neutron Detectors for Detection of Nuclear Materials at LANL Nuclear Physics (NP) NP Home About Research Facilities Science Highlights Benefits of NP Spinoff Applications Spinoff...

150

The Office of Nuclear Controls | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Controls | National Nuclear Security Administration Controls | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog The Office of Nuclear Controls Home > About Us > Our Programs > Nonproliferation > Nonproliferation & International Security > The Office of Nuclear Controls The Office of Nuclear Controls Certain terrorist groups and states are attempting to acquire WMD dual-use

151

Large Scale Weather Control Using Nuclear Reactors  

E-Print Network (OSTI)

It is pointed out that controlled release of thermal energy from fission type nuclear reactors can be used to alter weather patterns over significantly large geographical regions. (1) Nuclear heat creates a low pressure region, which can be used to draw moist air from oceans, onto deserts. (2) Creation of low pressure zones over oceans using Nuclear heat can lead to Controlled Cyclone Creation (CCC).(3) Nuclear heat can also be used to melt glaciers and control water flow in rivers.

Moninder Singh Modgil

2002-10-02T23:59:59.000Z

152

Recovery of fissile materials from nuclear wastes  

DOE Patents (OSTI)

A process is described 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.

Forsberg, Charles W.

1997-12-01T23:59:59.000Z

153

Recovery of fissile materials from nuclear wastes  

DOE Patents (OSTI)

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.

Forsberg, Charles W. (Oak Ridge, TN)

1999-01-01T23:59:59.000Z

154

GTRI: Removing Vulnerable Civilian Nuclear and Radiological Material |  

National Nuclear Security Administration (NNSA)

Removing Vulnerable Civilian Nuclear and Radiological Material | Removing Vulnerable Civilian Nuclear and Radiological Material | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Fact Sheets > GTRI: Removing Vulnerable Civilian Nuclear and Radiological Material Fact Sheet GTRI: Removing Vulnerable Civilian Nuclear and Radiological Material

155

GTRI: Removing Vulnerable Civilian Nuclear and Radiological Material |  

NLE Websites -- All DOE Office Websites (Extended Search)

Removing Vulnerable Civilian Nuclear and Radiological Material | Removing Vulnerable Civilian Nuclear and Radiological Material | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Fact Sheets > GTRI: Removing Vulnerable Civilian Nuclear and Radiological Material Fact Sheet GTRI: Removing Vulnerable Civilian Nuclear and Radiological Material

156

Nuclear Controls | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

17, 2013 NNSA, Republic of Korea Ministry Agree to Minimize Use of HEU in Nuclear Reactors Sep 3, 2013 NNSA Conducts Two Emergency Response Training Courses in Armenia Aug 29, 2013...

157

Radiation imaging technology for nuclear materials safeguards  

SciTech Connect

Gamma-ray and neutron imaging technology is emerging as a useful tool for nuclear materials safeguards. Principal applications include improvement in accuracy for nondestructive assay of heterogeneous material (e.g., residues) and wide-area imaging of nuclear material in facilities (e.g., holdup). Portable gamma cameras with gamma-ray spectroscopy are available commercially and are being applied to holdup measurements. The technology has the potential to significantly reduce effort and exposure in holdup campaigns; and, with imaging, some of the limiting assumptions required for conventional holdup analysis can be relaxed, resulting in a more general analysis. Methods to analyze spectroscopic-imaging data to assay plutonium and uranium in processing equipment are being development. Results of holdup measurements using a commercial, portable gamma-cameras are presented. The authors are also developing fast neutron imaging techniques for NDA, search, and holdup. Fast neutron imaging provides a direct measurement of the source of neutrons and is relatively insensitive to surroundings when compared to thermal or epithermal neutron imaging. The technology is well-suited for in-process inventory measurements and verification of materials in interim storage, for which gamma-ray measurements may be inadequate due to self-shielding. Results of numerical simulations to predict the performance of fast-neutron telescopes for safeguards applications are presented.

Prettyman, T.H.; Russo, P.A.; Cheung, C.C.; Christianson, A.D.; Feldman, W.C.; Gavron, A.

1997-12-01T23:59:59.000Z

158

Some political issues related to future special nuclear materials production  

Science Conference Proceedings (OSTI)

The Federal Government must take action to assure the future adequate supply of special nuclear materials for nuclear weapons. Existing statutes permit the construction of advanced defense production reactors and the reprocessing of commercial spent fuel for the production of special materials. Such actions would not only benefit the US nuclear reactor manufacturers, but also the US electric utilities that use nuclear reactors.

Peaslee, A.T. Jr.

1981-08-01T23:59:59.000Z

159

Turning a Nuclear Spotlight on Illegal Weapons Material  

Science Conference Proceedings (OSTI)

... research neutron source, which bathes material samples with low-energy neutrons. ... count acts as a unique signature of special nuclear material. ...

2013-09-12T23:59:59.000Z

160

The Nuclear Renaissance: A Challenge for the Materials Community  

Science Conference Proceedings (OSTI)

This program was developed by the Generation IV project management board on materials and ... Materials are the enablers for future nuclear technologies.

Note: This page contains sample records for the topic "nuclear material control" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
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161

Materials for Nuclear Power: A Brief Introduction - TMS  

Science Conference Proceedings (OSTI)

Feb 12, 2007 ... CITATION: Osman, T. M., "Materials for Nuclear Power: A Brief Introduction", Materials Technology@TMS, February 2007. Last Updated:...

162

Characterization of Nuclear Reactor Materials and Components with ...  

Science Conference Proceedings (OSTI)

About this Symposium. Meeting, 2013 TMS Annual Meeting & Exhibition. Symposium, Characterization of Nuclear Reactor Materials and Components with ...

163

Materials for Nuclear Power: Digital Resource Center - WEB ...  

Science Conference Proceedings (OSTI)

Feb 12, 2007 ... Select, Sandbox, Open Discussion Regarding Materials for Nuclear ... and fission products relevant for radioactive waste disposal projects.

164

Environmental Degradation of Materials in Nuclear Power Systems ...  

Science Conference Proceedings (OSTI)

Recapping the Environmental Degradation of Materials in Nuclear Power ... The conference hosted utility engineers, reactor vendor engineers, plant architect...

165

Multiscale Modeling of Defect Mechanics in Nuclear Materials  

Science Conference Proceedings (OSTI)

Abstract Scope, The key to developing advanced materials for nuclear applications is ... Physics-Based Homogenization of Random Continuum Microstructures.

166

Materials for Nuclear Power: Digital Resource Center - WEB ...  

Science Conference Proceedings (OSTI)

Jun 25, 2007 ... Select, Sandbox, Open Discussion Regarding Materials for Nuclear ... The Information Bridge contains documents and citations in physics,...

167

Materials Solutions for the Nuclear Renaissance - Programmaster.org  

Science Conference Proceedings (OSTI)

Nuclear reactors present a complex, challenging environment where innovations in materials science can provide for improved performance, efficiency and...

168

Environmental Degradation of Materials in Nuclear Power Systems ...  

Science Conference Proceedings (OSTI)

Environmental Degradation of Materials in Nuclear Power SystemsWater ... problems associated with spent fuel storage and radioactive waste disposal.

169

Characterization of Nuclear Reactor Materials and Components with ...  

Science Conference Proceedings (OSTI)

About this Symposium. Meeting, 2011 TMS Annual Meeting & Exhibition. Symposium, Characterization of Nuclear Reactor Materials and Components with ...

170

Implantation and Characterization of Helium in Nuclear Materials at ...  

Science Conference Proceedings (OSTI)

Symposium, Accelerated Materials Evaluation for Nuclear Application Utilizing Test Reactors, Ion Beam Facilities and Modeling. Presentation Title, Implantation

171

Materials for Nuclear Waste Disposal and Environmental Cleanup  

Science Conference Proceedings (OSTI)

Symposium, Materials for Nuclear Waste Disposal and Environmental Cleanup ... Secure and Certify Studies to Work on Production of Spiked Plutonium.

172

DOE M 441.1-1, Nuclear Material Packaging Manual  

Directives, Delegations, and Requirements

The manual provides detailed packaging requirements for protecting workers from exposure to nuclear materials stored outside of an approved engineered ...

2008-03-07T23:59:59.000Z

173

United States Department of Energy Nuclear Materials Stewardship  

Science Conference Proceedings (OSTI)

The Department of Energy launched the Nuclear Materials Stewardship Initiative in January 2000 to accelerate the work of achieving integration and cutting long-term costs associated with the management of the Department's nuclear materials, with the principal focus on excess materials. Management of nuclear materials is a fundamental and enduring responsibility that is essential to meeting the Department's national security, nonproliferation, energy, science, and environmental missions into the distant future. The effective management of nuclear materials is important for a set of reasons: (1) some materials are vital to our national defense; (2) the materials pose physical and security risks; (3) managing them is costly; and (4) costs are likely to extend well into the future. The Department currently manages nuclear materials under eight programs, with offices in 36 different locations. Through the Nuclear Materials Stewardship Initiative, progress was during calendar year 20 00 in achieving better coordination and integration of nuclear materials management responsibilities and in evaluating opportunities to further coordinate and integrate cross-program responsibilities for the treatment, storage, and disposition of excess nuclear materials. During CY 2001 the Departmental approach to nuclear materials stewardship changed consistent with the business processes followed by the new administration. This paper reports on the progress of the Nuclear Materials Stewardship Initiative in evaluating and implementing these opportunities, and the remaining challenges in integrating the long-term management of nuclear materials.

Newton, J. W.

2002-02-27T23:59:59.000Z

174

Magnetic nuclear core restraint and control  

DOE Patents (OSTI)

A lateral restraint and control system for a nuclear reactor core adaptable to provide an inherent decrease of core reactivity in response to abnormally high reactor coolant fluid temperatures. An electromagnet is associated with structure for radially compressing the core during normal reactor conditions. A portion of the structures forming a magnetic circuit are composed of ferromagnetic material having a curie temperature corresponding to a selected coolant fluid temperature. Upon a selected signal, or inherently upon a preselected rise in coolant temperature, the magnetic force is decreased a given amount sufficient to relieve the compression force so as to allow core radial expansion. The expanded core configuration provides a decreased reactivity, tending to shut down the nuclear reaction.

Cooper, Martin H. (Monroeville, PA)

1979-01-01T23:59:59.000Z

175

Implementation Plan and Initial Development of Nuclear Concrete Materials  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Implementation Plan and Initial Development of Nuclear Concrete Implementation Plan and Initial Development of Nuclear Concrete Materials Database for Light Water Reactor Sustainability Program Implementation Plan and Initial Development of Nuclear Concrete Materials Database for Light Water Reactor Sustainability Program 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 using the ORNL materials database infrastructure established for the Gen IV Materials Handbook to achieve cost reduction and development efficiency. In Phase I, a static database will be developed to manage searchable documents from the Structural Materials Handbook that contains information on nuclear concrete

176

Implementation Plan and Initial Development of Nuclear Concrete Materials  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Implementation Plan and Initial Development of Nuclear Concrete Implementation Plan and Initial Development of Nuclear Concrete Materials Database for Light Water Reactor Sustainability Program Implementation Plan and Initial Development of Nuclear Concrete Materials Database for Light Water Reactor Sustainability Program 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 using the ORNL materials database infrastructure established for the Gen IV Materials Handbook to achieve cost reduction and development efficiency. In Phase I, a static database will be developed to manage searchable documents from the Structural Materials Handbook that contains information on nuclear concrete

177

Nuclear Resonance Fluorescence for Materials Assay  

E-Print Network (OSTI)

et al. Investigation of Nuclear Structure by Resonance1996, pp. G. Warren et al. Nuclear Resonance Fluorescenceof 235U IEEE Nuclear Science Symposium 2006, pp. 914. W.

Quiter, Brian J.

2010-01-01T23:59:59.000Z

178

Materials Development for Nuclear Applications and Extreme ...  

Science Conference Proceedings (OSTI)

Aladar A Csontos, Nuclear Regulatory Commission ... on lifetime extension of existing nuclear reactors and meeting the challenges of future nuclear endeavors

179

Unclassified Controlled Nuclear Information Document Markings: A Brief Summary  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Unclassified Controlled Nuclear Unclassified Controlled Nuclear Information (UCNI) Document Markings: A Brief Summary U.S. Department of Energy Classification Training Institute Office of Quality Management Office of Classification Office of Health, Safety and Security November 2011 Unclassified Controlled Nuclear Information (UCNI) Document Markings: A Brief Summary Prepared by: Office of Quality Management Office of Classification U.S. Department of Energy 1000 Independence Avenue, SW. Washington, D.C. 20585-1290 U C N I This document contains UCNI. How do I mark it? Do I need additional markings if it contains OUO? Table of Contents Marking UCNI Documents and Material .................................................... 1

180

GTRI's Nuclear and Radiological Material Removal | National Nuclear...  

National Nuclear Security Administration (NNSA)

Removal | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our...

Note: This page contains sample records for the topic "nuclear material control" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

Material Removal and Disposition | National Nuclear Security...  

National Nuclear Security Administration (NNSA)

Removal and Disposition | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

182

Molecular forensic science of nuclear materials  

SciTech Connect

We are interested in applying our understanding of actinide chemical structure and bonding to broaden the suite of analytical tools available for nuclear forensic analyses. Uranium- and plutonium-oxide systems form under a variety of conditions, and these chemical species exhibit some of the most complex behavior of metal oxide systems known. No less intriguing is the ability of AnO{sub 2} (An: U, Pu) to form non-stoichiometric species described as AnO{sub 2+x}. Environmental studies have shown the value of utilizing the chemical signatures of these actinide oxides materials to understand transport following release into the environment. Chemical speciation of actinide-oxide samples may also provide clues as to the age, source, process history, or transport of the material. The scientific challenge is to identify, measure and understand those aspects of speciation of actinide analytes that carry information about material origin and history most relevant to forensics. Here, we will describe our efforts in material synthesis and analytical methods development that we will use to provide the fundamental science required to characterize actinide oxide molecular structures for forensics science. Structural properties and initial results to measure structural variability of uranium oxide samples using synchrotron-based X-ray Absorption Fine Structure will be discussed.

Wilkerson, Marianne Perry [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

183

SECURITY AND CONTROL OF NUCLEAR EXPLOSIVES AND NUCLEAR WEAPONS  

National Nuclear Security Administration (NNSA)

http://www.nnsa.energy.gov Office of Nuclear Weapon Surety and Quality http://www.nnsa.energy.gov Office of Nuclear Weapon Surety and Quality SUPPLEMENTAL DIRECTIVE Approved: 7-7-11 IMPLEMENTATION AND EVALUATION OF CONTROLS TO PREVENT DELIBERATE UNAUTHORIZED USE NATIONAL NUCLEAR SECURITY ADMINISTRATION Office of Defense Programs NA SD 452.4 NA SD 452.4 1 7-7-11 IMPLEMENTATION AND EVALUATION OF CONTROLS TO PREVENT DELIBERATE UNAUTHORIZED USE 1. PURPOSE. This NNSA Supplemental Directive (SD) supports the requirements of DOE O 452.4B, Security and Use Control of Nuclear Explosives and Nuclear Weapons. Specifically, this SD supports the Order's requirements to implement deliberate unauthorized use (DUU) preventive measures for nuclear explosive operations (NEO) and associated activities and to perform independent evaluations to determine if NEOs

184

Office of Material Consolidation & Civilian Sites | National Nuclear  

National Nuclear Security Administration (NNSA)

Material Consolidation & Civilian Sites | National Nuclear Material Consolidation & Civilian Sites | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Office of Material Consolidation & Civilian Sites Home > About Us > Our Programs > Nonproliferation > Nuclear Nonproliferation Program Offices > Office of International Material

185

Assessment tool for nuclear material acquisition pathways  

E-Print Network (OSTI)

An assessment methodology has been developed at Texas A&M University for predicting weapons useable material acquisition by a terrorist organization or rogue state based on an acquisition network simulation. The network has been designed to include all of the materials, facilities, and expertise (each of which are represented by a unique node) that must be obtained to acquire Special Nuclear Material (SNM). Using various historical cases and open source expert opinion, the resources required to successfully obtain the goal of every node within the network was determined. A visual representation of the network was created within Microsoft Visio and uses Visual Basic for Applications (VBA) to analyze the network. This tool can be used to predict the most likely pathway(s) that a predefined organization would take in attempting to acquire SNM. The methodology uses the resources available to the organization, along with any of the nodes to which the organization may already have access, to determine which path the organization is most likely to attempt. Using this resource based decision model, various sample simulations were run to exercise the program. The results of these simulations were in accordance with what was expected for the resources allocated to the organization being modeled. The program was demonstrated to show that it was capable of taking many complex resources considerations into account and modeled them accurately.

Ford, David Grant

2008-05-01T23:59:59.000Z

186

AEC and control of nuclear weapons  

NLE Websites -- All DOE Office Websites (Extended Search)

control of nuclear weapons The Atomic Energy Commission took control of the atomic energy project known originally as the Manhattan Project on January 1, 1947. This shift from the...

187

Reactivity control assembly for nuclear reactor  

DOE Patents (OSTI)

Reactivity control assembly for nuclear reactor comprises supports stacked above reactor core for holding control rods. Couplers associated with the supports and a vertically movable drive shaft have lugs at their lower ends for engagement with the supports.

Bollinger, Lawrence R. (Schenectady, NY)

1984-01-01T23:59:59.000Z

188

Materials for Nuclear Power: Digital Resource Center -- Nuclear ...  

Science Conference Proceedings (OSTI)

WEB RESOURCE: Thermodynamics of Nuclear Fuels ... A brief introduction to nuclear physics, 0, 851, Lynne Robinson, 2/19/2007 9:38 AM by Lynne Robinson

189

MATERIAL CONTROL & ACCOUNTING Refresher Training 2004  

National Nuclear Security Administration (NNSA)

by a Fuel Fabricator Global Nuclear Fuel Rose Martyn NMMSS Upgrade Impact at GNF * 741 Text File * 741 Printed Form * 742 Report * Country Control Balances * Customers U ranium B...

190

Nuclear Resonance Fluorescence for Materials Assay  

E-Print Network (OSTI)

and safeguards for nuclear fuel cycles Examples of age-PECIFIC E XAMPLES A. Spent Nuclear Fuel A critical componentnuclear safeguards including measuring uranium enrichments, spent fuel

Quiter, Brian J.

2010-01-01T23:59:59.000Z

191

Materials Science Challenges for Nuclear Applications  

Science Conference Proceedings (OSTI)

Aladar A. Csontos, U.S. Nuclear Regulatory Commission. Scope, Worldwide expansion of nuclear energy has been proposed to address rising global energy ...

192

The Nuclear Material Focus Area Roadmapping Process Utilizing Environmental Management Complex-Wide Nuclear Material Disposition Pathways  

SciTech Connect

This paper describes the process that the Nuclear Materials Focus Area (NMFA) has developed and utilizes in working with individual Department of Energy (DOE) sites to identify, address, and prioritize research and development efforts in the stabilization, disposition, and storage of nuclear materials. By associating site technology needs with nuclear disposition pathways and integrating those with site schedules, the NMFA is developing a complex wide roadmap for nuclear material technology development. This approach will leverage technology needs and opportunities at multiple sites and assist the NMFA in building a defensible research and development program to address the nuclear material technology needs across the complex.

Sala, D. R.; Furhman, P.; Smith, J. D.

2002-02-26T23:59:59.000Z

193

Integrated Computational Modeling of Materials for Nuclear Energy  

Science Conference Proceedings (OSTI)

Nuclear fuel and primary cooling system structural components are exposed to elevated ... models for safety and performance evaluation of nuclear reactors but also for the ... Continuum Theory of Defects and Materials Response to Irradiation

194

Special Nuclear Material Portal Monitoring at the Nevada Test Site  

SciTech Connect

Prior to April 2007, acceptance and performance testing of the various Special Nuclear Material (SNM) monitoring devices at the Nevada Test Site (NTS) was performed by the Radiological Health Instrumentation department. Calibration and performance testing on the PM-700 personnel portal monitor was performed, but there was no test program for the VM-250 vehicle portal monitor. The handheld SNM monitors, the TSA model 470B, were being calibrated annually, but there was no performance test program. In April of 2007, the Material Control and Accountability Manager volunteered to take over performance testing of all SNM portal monitors at NTS in order to strengthen the program and meet U.S. Department of Energy Order requirements. This paper will discuss the following activities associated with developing a performance testing program: changing the culture, learning the systems, developing and implementing procedures, troubleshooting and repair, validating the process, physical control of equipment, acquisition of new systems, and implementing the performance test program.

DeAnn Long; Michael Murphy

2008-07-01T23:59:59.000Z

195

PLANNING AND COORDINATION OF ACTIVITIES SUPPORTING THE RUSSIAN SYSTEM OF CONTROL AND ACCOUNTING OF NUCLEAR MATERIALS AT ROSATOM FACILITIES IN THE FRAMEWORK OF THE U.S.-RUSSIAN COOPERATION.  

SciTech Connect

The MC&A Equipment and Methodological Support Strategic Plan (MEMS SP) for implementing modern MC&A equipment and methodologies at Rosatom facilities has been developed within the framework of the U.S.-Russian MPC&A Program. This plan developed by the Rosatom's Russian MC&A Equipment and Methodologies (MEM) Working Group and is coordinated by that group with support and coordination provided by the MC&A Measurements Project, Office of National Infrastructure and Sustainability, US DOE. Implementation of different tasks of the MEMS Strategic Plan is coordinated by Rosatom and US-DOE in cooperation with different U.S.-Russian MC&A-related working groups and joint site project teams. This cooperation allows to obtain and analyze information about problems, current needs and successes at Rosatom facilities and facilitates solution of the problems, satisfying the facilities' needs and effective exchange of expertise and lessons learned. The objective of the MEMS Strategic Plan is to enhance effectiveness of activities implementing modern equipment and methodologies in the Russian State MC&A system. These activities are conducted within the joint Russian-US MPC&A program aiming at reduction of possibility for theft or diversion of nuclear materials and enhancement of control of nuclear materials.

SVIRIDOVA, V.V.; ERASTOV, V.V.; ISAEV, N.V.; ROMANOV, V.A.; RUDENKO, V.S.; SVIRIDOV, A.S.; TITOV, G.V.; JENSEN, B.; NEYMOTIN, L.; SANDERS, J.

2005-05-16T23:59:59.000Z

196

Nuclear Maintenance Applications Center: Material Handling Application Guide  

Science Conference Proceedings (OSTI)

Although the majority of the material handling activities at nuclear power plant sites are similar to the material handling activities in many other industries, there are several differences unique to the nuclear power industry. This guide to material handling equipment and its safe and effective operation at nuclear plants covers basic common practices while taking into account those unique differences. Recent industry experiences provide context for the guidance in the report.

2007-11-30T23:59:59.000Z

197

Absolute nuclear material assay using count distribution (LAMBDA) space  

DOE Patents (OSTI)

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.

Prasad, Manoj K. (Pleasanton, CA); Snyderman, Neal J. (Berkeley, CA); Rowland, Mark S. (Alamo, CA)

2012-06-05T23:59:59.000Z

198

Environmental Degradation of Materials in Nuclear Systems XII (2007)  

Science Conference Proceedings (OSTI)

Apr 1, 2007 ... Print Book: Environmental Degradation of Materials in Nuclear Power Systems- Water Reactors IX (1999). Print Book: Fundamentals of...

199

New RFID technology tracks and monitors nuclear materials | Argonne...  

NLE Websites -- All DOE Office Websites (Extended Search)

New RFID technology tracks and monitors nuclear materials By Jared Sagoff * March 24, 2009 Tweet EmailPrint Advancement has applications in many areas involving remote sensing...

200

Nuclear Materials Management & Safeguards System CHANGE OF PROJECT...  

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:...

Note: This page contains sample records for the topic "nuclear material control" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

Materials for Nuclear Power: Digital Resource Center - WEB ...  

Science Conference Proceedings (OSTI)

Feb 16, 2007 ... Select, Sandbox, Open Discussion Regarding Materials for Nuclear ... This web site, from the American Institute of Physics, documents the...

202

Materials for Nuclear Power: Digital Resource Center - ARTICLE ...  

Science Conference Proceedings (OSTI)

Feb 19, 2007 ... Select, Sandbox, Open Discussion Regarding Materials for Nuclear Power ... This article reviews how Albert Einstein revolutionized physics by...

203

Materials for Nuclear Power: Digital Resource Center - BOOK ...  

Science Conference Proceedings (OSTI)

Feb 12, 2007 ... Select, Sandbox, Open Discussion Regarding Materials for Nuclear Power ... NATO Science Series II:Mathematics, Physics and Chemistry, Vol.

204

Discussions@TMS - Materials Issues for Advanced Nuclear Systems ...  

Science Conference Proceedings (OSTI)

Feb 27, 2007... for applications in high temperature nuclear reactor core materials, ... Theory of RIS was introduced and how over-size solute additions can...

205

Materials for Nuclear Power: Digital Resource Center Text Topic - TMS  

Science Conference Proceedings (OSTI)

Mar 28, 2007 ... Scientists and engineers concerned with the environmental ... of Materials in Nuclear Power SystemsWater Reactors (Warrendale, PA: TMS,...

206

Materials for Nuclear Power: Digital Resource Center - WEB ...  

Science Conference Proceedings (OSTI)

Feb 12, 2007 ... A collection of thermodynamic databases. This site is not focused entirely on nuclear materials, but information can be "mined" from the "Data...

207

Materials for Nuclear Power: Digital Resource Center - WEB ...  

Science Conference Proceedings (OSTI)

Feb 16, 2007 ... This web site offers a number of supplemental materials related to the study and practice of nuclear chemistry. It includes audio and video files,...

208

Materials for Nuclear Power: Digital Resource Center - ARTICLES ...  

Science Conference Proceedings (OSTI)

Sep 12, 2007 ... Use the link provided below to access the following articles featured in the April 2007 issue of JOM: "Materials for Advanced Nuclear Systems,"...

209

Materials for Nuclear Power: Digital Resource Center - WEB ... - TMS  

Science Conference Proceedings (OSTI)

Feb 12, 2007 ... PDFs of lecture notes and readings for this undergraduate course covering materials issues in nuclear power systems. Topics include:...

210

Materials for Nuclear Power: Digital Resource Center - WEB ... - TMS  

Science Conference Proceedings (OSTI)

May 7, 2007 ... This link leads to the database overview page of the Thermo-Calc Software web site. A listing of databases for nuclear materials can be...

211

Materials for Nuclear Power: Digital Resource Center - TMS  

Science Conference Proceedings (OSTI)

Spacer 62115 users are registered to the Materials for Nuclear Power: Digital Resource Center forum. Spacer There are currently 0 users logged in. Spacer...

212

Characterization of Nuclear Reactor Materials and Components with ...  

Science Conference Proceedings (OSTI)

Mar 6, 2013 ... Characterization of Nuclear Reactor Materials and Components with ... Results are discussed in terms of existing theoretical models for hydride...

213

Light Water Reactor Materials for Commercial Nuclear Power ...  

Science Conference Proceedings (OSTI)

Presentation Title, Light Water Reactor Materials for Commercial Nuclear ... First- Principles Theory of Magnetism, Crystal Field and Phonon Spectrum of UO2.

214

Materials for Nuclear Power: Digital Resource Center - SELECTED ...  

Science Conference Proceedings (OSTI)

Jul 6, 2007 ... Select, Sandbox, Open Discussion Regarding Materials for Nuclear Power ... Instructions for Accessing Reports: Because of security features in...

215

Materials for Nuclear Power: Digital Resource Center - BOOK ...  

Science Conference Proceedings (OSTI)

Jun 22, 2007 ... Citation: Scientific Basis for Nuclear Waste Management XXVI. Vol. 757. Eds., R. Finch, D. Bullen. Warrendale, PA: Materials Research Society,...

216

Materials for Nuclear Power: Digital Resource Center - WEB ...  

Science Conference Proceedings (OSTI)

May 10, 2007 ... This general overview of nuclear materials research at MIT briefly describes the department's work in "Irradiation-induced Degradation of...

217

Materials for Nuclear Power: Digital Resource Center - BOOK ...  

Science Conference Proceedings (OSTI)

Jun 22, 2007 ... Citation: Scientific Basis for Nuclear Waste Management XXIX. Vol. 932. Ed., P. Van Iseghem. Warrendale, PA: Materials Research Society,...

218

Spark Plasma Sintering of Next Generation Nuclear Materials  

Science Conference Proceedings (OSTI)

... Spark Plasma Sintering of Next Generation Nuclear Materials. Author(s), Daniel Osterberg, Jeff Perkins, Matt Luke, Brian Jaques, Michael F Hurley, Darryl Butt.

219

DOE O 410.2, Management of Nuclear Materials  

Directives, Delegations, and Requirements

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

2009-08-17T23:59:59.000Z

220

Materials for Nuclear Power: Digital Resource Center - WEBCAST ...  

Science Conference Proceedings (OSTI)

A tutorial on the effects of radiation on strucutral materials for nuclear energy applications. Created On: 5/25/2007 7:35 AM, Topic View: Linear, Threading...

Note: This page contains sample records for the topic "nuclear material control" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

Materials for Nuclear Power: Digital Resource Center ... - TMS  

Science Conference Proceedings (OSTI)

WEB RESOURCE: Nuclear Materials, Science and Technology Group Research group of Oak Ridge National Laboratory, 0, 708, Lynne Robinson, 2/19/2007...

222

Nuclear Reactor Materials at the Atomic Scale - Programmaster.org  

Science Conference Proceedings (OSTI)

Presentation Title, Nuclear Reactor Materials at the Atomic Scale ... Study of the Interaction of Solutes with Interfaces in Iron Using Density-Functional Theory.

223

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

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Works With Kazakhstan to Stop Nuclear and Radioactive Material 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 of Kazakhstan had been signed to create a partnership under the Second Line of Defense program. U.S. Ambassador Ordway joined Kazakhstan Customs Control Committee Chairman Askar Shakirov in signing the accord. The agreement will pave the way for NNSA to work collaboratively with the Kazakhstan Customs Control Committee

224

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

National Nuclear Security Administration (NNSA)

Insider Threat to Nuclear and Radiological Materials: Fact Sheet | National Insider Threat to Nuclear and Radiological Materials: Fact Sheet | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Fact Sheets > Insider Threat to Nuclear and Radiological Materials: ... Fact Sheet Insider Threat to Nuclear and Radiological Materials: Fact Sheet

225

Tiny device can detect hidden nuclear weapons, materials  

NLE Websites -- All DOE Office Websites (Extended Search)

Tiny Tiny device can detect hidden nuclear weapons, materials Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library About Nuclear Energy Nuclear Reactors Designed by Argonne Argonne's Nuclear Science and Technology Legacy Opportunities within NE Division Visit Argonne Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Celebrating the 70th Anniversary of Chicago Pile 1 (CP-1) Argonne OutLoud on Nuclear Energy Argonne Energy Showcase 2012 Highlights Bookmark and Share Tiny device can detect hidden nuclear weapons, materials This tiny wafer can detect hidden nuclear weapons and materials NUCLEAR DETECTOR -- This small wafer could become the key component in

226

Microbial Effects on Nuclear Waste Packaging Materials  

DOE Green Energy (OSTI)

Microorganisms may enhance corrosion of components of planned engineered barriers within the proposed nuclear waste repository at Yucca Mountain (YM). Corrosion could occur either directly, through processes collectively known as Microbiologically Influenced Corrosion (MIC), or indirectly, by adversely affecting the composition of water or brines that come into direct contact with engineered barrier surfaces. Microorganisms of potential concern (bacteria, archea, and fungi) include both those indigenous to Yucca Mountain and those that infiltrate during repository construction and after waste emplacement. Specific aims of the experimental program to evaluate the potential of microorganisms to affect damage to engineered barrier materials include the following: Indirect Effects--(1) Determine the limiting factors to microbial growth and activity presently in the YM environment. (2) Assess these limiting factors to aid in determining the conditions and time during repository evolution when MIC might become operant. (3) Evaluate present bacterial densities, the composition of the YM microbial community, and determining bacterial densities if limiting factors are overcome. During a major portion of the regulatory period, environmental conditions that are presently extant become reestablished. Therefore, these studies ascertain whether biomass is sufficient to cause MIC during this period and provide a baseline for determining the types of bacterial activities that may be expected. (4) Assess biogenic environmental effects, including pH, alterations to nitrate concentration in groundwater, the generation of organic acids, and metal dissolution. These factors have been shown to be those most relevant to corrosion of engineered barriers. Direct Effects--(1) Characterize and quantify microbiological effects on candidate containment materials. These studies were carried out in a number of different approaches, using whole YM microbiological communities, a subset of YM bacteria, and select reference organisms. Studies were carried out to determine morphological alterations to materials surfaces and using electrochemical methods to help quantify effects and modes of MIC, and to provide additional alternative means of evaluating MIC effects. They were carried out only under conservative conditions (low temperature, saturated conditions); thus, resulting conclusions may be considered an upper bound of potential biological effects on tested materials.

Horn, J; Martin, S; Carrillo, C; Lian, T

2005-07-22T23:59:59.000Z

227

Materials Development for Nuclear Applications and Extreme ...  

Science Conference Proceedings (OSTI)

Presentations that combine experiment with theory, modeling and simulation to enhance our understanding of ... Lifetime extension of existing nuclear reactors

228

Materials Development and Degradation Management for Nuclear ...  

Science Conference Proceedings (OSTI)

Mar 31, 2013 ... Presentations that combine experiment with theory, modeling and ... for Accident Tolerant Fuel Cladding in Commercial Nuclear Reactors.

229

Switched Control of Electron Nuclear Spin Systems  

E-Print Network (OSTI)

In this article, we study control of electron-nuclear spin dynamics at magnetic field strengths where the Larmor frequency of the nucleus is comparable to the hyperfine coupling strength. The quantization axis for the nuclear spin differs from the static B_0 field direction and depends on the state of the electron spin. The quantization axis can be switched by flipping the state of electron spin, allowing for universal control on nuclear spin states. We show that by performing a sequence of flips (each followed by a suitable delay), we can perform any desired rotation on the nuclear spins, which can also be conditioned on the state of the electron spin. These operations, combined with electron spin rotations can be used to synthesize any unitary transformation on the coupled electron-nuclear spin system. We discuss how these methods can be used for design of experiments for transfer of polarization from the electron to the nuclear spins.

Navin Khaneja

2007-07-11T23:59:59.000Z

230

Materials for Nuclear Power: Digital Resource Center -- Materials ...  

Science Conference Proceedings (OSTI)

WEB RESOURCE: Nuclear Data Services Atomic, molecular and other technical data from the International Atomic Energy Agency, 0, 759, Todd Osman...

231

Materials Handbook for Nuclear Plant Pressure Boundary Applications (2013)  

Science Conference Proceedings (OSTI)

Utility engineers require accurate structural materials properties and performance data to make decisions regarding the adequacy of materials for nuclear power applications. To meet this need, the Electric Power Research Institute (EPRI) publishes the Materials Handbook for Nuclear Plant Pressure Boundary Applications, which has been updated and revised since its initial publication in 1998. The primary focus of the handbook is on pressure boundary materials such as those used for piping ...

2013-03-28T23:59:59.000Z

232

Vapor etching of nuclear tracks in dielectric materials  

DOE Patents (OSTI)

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.

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

2000-01-01T23:59:59.000Z

233

Variable flow control for a nuclear reactor control rod  

DOE Patents (OSTI)

A variable flow control for a control rod assembly of a nuclear reactor that depends on turbulent friction though an annulus. The annulus is formed by a piston attached to the control rod drive shaft and a housing or sleeve fitted to the enclosure housing the control rod. As the nuclear fuel is burned up and the need exists for increased reactivity, the control rods are withdrawn, which increases the length of the annulus and decreases the rate of coolant flow through the control rod assembly.

Carleton, Richard D. (Pittsburgh, PA); Bhattacharyya, Ajay (Vasteras, SE)

1978-01-01T23:59:59.000Z

234

Loose Nukes: Nuclear Material Security in G.P.Gilfoyle  

E-Print Network (OSTI)

Not supported by administration. No change. NPT Non-Proliferation Treaty See CTBT. No change. ABM Anti of a nuclear weapon by an adversary could have a devastating influence on US security and non-proliferation.A.Parmentola, Using Nuclear Materials to Prevent Nuclear Proliferation, Science and Global Security, 9, 81 (2001). #12

Gilfoyle, Jerry

235

GEOCHEMICAL CONTROLS ON NUCLEAR MAGNETIC RESONANCE MEASUREMENTS  

Science Conference Proceedings (OSTI)

Proton nuclear magnetic resonance (NMR) is used in the Earth Sciences as a means of obtaining information about the molecular-scale environment of fluids in porous geological materials. Laboratory experiments were conducted to advance our fundamental understanding of the link between the NMR response and the geochemical properties of geological materials. In the first part of this research project, we studied the impact of both the surface-area-to-volume ratio (S/V) of the pore space and the surface relaxivity on the NMR response of fluids in sand-clay mixtures. This study highlighted the way in which these two parameters control our ability to use NMR measurements to detect and quantify fluid saturation in multiphase saturated systems. The second part of the project was designed to explore the way in which the mineralogic form of iron, as opposed to simply the concentration of iron, affects the surface relaxation rate and, more generally, the NMR response of porous materials. We found that the magnitude of the surface relaxation rate was different for the various iron-oxide minerals because of changes in both the surface-area-to-volume ratio of the pore space, and the surface relaxivity. Of particular significance from this study was the finding of an anomalously large surface relaxivity of magnetite compared to that of the other iron minerals. Differences in the NMR response of iron minerals were seen in column experiments during the reaction of ferrihydrite-coated quartz sand with aqueous Fe(II) solutions to form goethite, lepidocrocite and magnetite; indicating the potential use of NMR as a means of monitoring geochemical reactions. The final part of the research project investigated the impact of heterogeneity, at the pore-scale, on the NMR response. This work highlighted the way in which the geochemistry, by controlling the surface relaxivity, has a significant impact on the link between NMR data and the microgeometry of the pore space.

Rosemary Knight

2008-08-25T23:59:59.000Z

236

Neutron absorbing coating for nuclear criticality control  

DOE Patents (OSTI)

A neutron absorbing coating for use on a substrate, and which provides nuclear criticality control is described and which includes a nickel, chromium, molybdenum, and gadolinium alloy having less than about 5% boron, by weight.

Mizia, Ronald E. (Idaho Falls, ID); Wright, Richard N. (Idaho Falls, ID); Swank, William D. (Idaho Falls, ID); Lister, Tedd E. (Idaho Falls, ID); Pinhero, Patrick J. (Idaho Falls, ID)

2007-10-23T23:59:59.000Z

237

Nondestructive assay of fissile material samples in support of nuclear safeguards  

SciTech Connect

From nuclear science symposium; San Francisco, California, USA (14 Nov 1973). Samples of fissile material can be assayed by bombarding with 300- to 600- keV neutrons and counting delayed neutrons from fission. Interrogating neutron energy selection is based upon considerations of sample penetrability and insensitivity of response to nonfissile isotopes. Significant cost savings in nuclear safeguards and quality control are possible. (auth)

Evans, A.E. Jr.

1973-01-01T23:59:59.000Z

238

Los Alamos identifies internal material control issue  

NLE Websites -- All DOE Office Websites (Extended Search)

Internal material control issue Internal material control issue Los Alamos identifies internal material control issue The error relates to internal inventory and accounting that documents movement of sensitive materials within a small portion of Technical Area 55. February 26, 2009 Los Alamos National Laboratory sits on top of a once-remote mesa in northern New Mexico with the Jemez mountains as a backdrop to research and innovation covering multi-disciplines from bioscience, sustainable energy sources, to plasma physics and new materials. Los Alamos National Laboratory sits on top of a once-remote mesa in northern New Mexico with the Jemez mountains as a backdrop to research and innovation covering multi-disciplines from bioscience, sustainable energy sources, to plasma physics and new materials.

239

Nuclear Energy Advisory Committee Meeting Materials | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Energy Advisory Committee Meeting Materials Nuclear Energy Advisory Committee Meeting Materials Nuclear Energy Advisory Committee Meeting Materials November 26, 2013 MEETING MATERIALS: DECEMBER 19, 2013 Washington Marriott at Metro Center Ballroom A 775 12th Street, NW Washington, DC 20005 June 13, 2013 MEETING MATERIALS: JUNE 13, 2013 L'Enfant Plaza Hotel Ballroom D, (Main Floor) Washington, D.C. 20024 December 6, 2012 Meeting Materials: December 6, 2012 L'Enfant Plaza Hotel Quorum Room, (Main Floor) Washington, D.C. 20024 June 12, 2012 Meeting Materials: June 12, 2012 L'Enfant Plaza Hotel Monet Ballroom, (2nd Floor), Washington, D.C. 20024 December 13, 2011 Meetings Materials: December 13, 2011 L'Enfant Plaza Hotel Ballroom A - 1st Floor Washington, D.C. 20024 June 15, 2011 Meeting Materials: June 15, 2011 L'Enfant Plaza Hotel

240

Materials for Nuclear Power: Digital Resource Center -- Nuclear ...  

Science Conference Proceedings (OSTI)

WEB RESOURCE: Nuclear Science and Technology Lecture notes and presentations, 0, 779, Lynne Robinson, 2/19/2007 8:55 AM by Lynne Robinson.

Note: This page contains sample records for the topic "nuclear material control" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

Materials for Nuclear Power: Digital Resource Center -- The Nuclear ...  

Science Conference Proceedings (OSTI)

REPORT: Technology and Applied R&D Needs for Advanced Nuclear Energy Systems A resource document for the Workshop on Basic Research Needs for...

242

Materials Science of Nuclear Waste Management I  

Science Conference Proceedings (OSTI)

Mar 6, 2013 ... Separation of the nuclear waste stream into actinides and fission products offers new opportunities for development of ceramic waste forms.

243

Nuclear Fuel Materials - Programmaster.org  

Science Conference Proceedings (OSTI)

Mar 3, 2011 ... Various metallic nuclear fuels are bcc alloys of uranium that swell under ... that currently employ fuels containing highly enriched uranium.

244

Open Discussion Regarding Materials for Nuclear Power  

Science Conference Proceedings (OSTI)

Jan 4, 2008 ... What long-term nuclear waste storage solution do you believe to be most promising? A JOM Readers Survey Question, 0, 920, Todd Osman...

245

Materials for Nuclear Power: Digital Resource Center ...  

Science Conference Proceedings (OSTI)

Mar 5, 2008 ... An overview presentation covering drivers for the Nuclear Renaissance and the path forward for nucleaer power in the United States.

246

Materials and Processes to Immobilize Nuclear Waste  

Science Conference Proceedings (OSTI)

Oct 8, 2012 ... While borosilicate glass is widely regarded as baseline technology for nuclear waste immobilisation, there are a wide range of such wastes that...

247

Fissile Material Disposition (MD) - Nuclear Engineering Division...  

NLE Websites -- All DOE Office Websites (Extended Search)

a legacy of surplus fissile materials (primarily weapons-grade plutonium and highly enriched uranium) in the United States and the former Soviet Union. These materials pose a...

248

Nuclear reaction analysis of hydrogen in SSC beam pipe materials  

DOE Green Energy (OSTI)

To control the photodesorption of molecular hydrogen, it is advantageous to reduce the amount of hydrogen in candidate SSC beam pipe materials and identify those procedures that: (1) lead to contamination of the beam pipe surface or materials, (2) would reduce the amount of hydrogen on the surface or in the bulk and (3) could be used for in-situ cleaning during Collider assembly or during Collider maintenance. Nuclear Reaction Analysis (NRA) can be used to quantitatively measure the amount of hydrogen on the surface or within half a micron of the surface. The present report discusses data that has been obtained for candidate SSC beam pipe materials (Nitronix 40 Stainless Steel, Nitronix 40 SS coated with electrodeposited copper (Silvex process)), oxygen-free high conductivity copper (Hitachi 101 OFHC) and several miscellaneous samples. The work demonstrates the potential of the technique for characterizing the hydrogen concentration of accelerator beam pipe materials, for assisting in the development of better vacuum system materials for TeV-scale accelerators, and for the development of better beam pipe construction or maintenance procedures for future accelerator projects.

Ruckman, M.W.; Strongin, M. [Brookhaven National Lab., Upton, NY (United States); Lanford, W.A. [State Univ. of New York, Albany, NY (United States). Dept. of Physics

1993-12-31T23:59:59.000Z

249

A sensor-based automation system for handling nuclear materials  

Science Conference Proceedings (OSTI)

An automated system is being developed for handling large payloads of radioactive nuclear materials in an analytical laboratory. The automation system performs unpacking and repacking of payloads from shipping and storage containers, and delivery of the payloads to the stations in the laboratory. The system uses machine vision and force/torque sensing to provide sensor-based control of the automation system in order to enhance system safety, flexibility, and robustness, and achieve easy remote operation. The automation system also controls the operation of the laboratory measurement systems and the coordination of them with the robotic system. Particular attention has been given to system design features and analytical methods that provide an enhanced level of operational safety. Independent mechanical gripper interlock and tool release mechanisms were designed to prevent payload mishandling. An extensive Failure Modes and Effects Analysis of the automation system was developed as a safety design analysis tool.

Drotning, W.; Kimberly, H.; Wapman, W.; Darras, D. [and others

1997-03-01T23:59:59.000Z

250

Special Nuclear Materials: EM Manages Plutonium, Highly Enriched Uranium  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Materials & Waste » 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 welded 3013 containers that are nested in 9975 shipping containers. 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 welded 3013 containers that are nested in 9975 shipping

251

Commercial Products Show Potential to serve as Nuclear Material and  

NLE Websites -- All DOE Office Websites (Extended Search)

Commercial Products Show Potential to serve as Nuclear Material and Commercial Products Show Potential to serve as Nuclear Material and Activity Monitoring Technologies | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > NNSA Blog > Commercial Products Show Potential to serve as ... Commercial Products Show Potential to serve as Nuclear Material and

252

Commercial Products Show Potential to serve as Nuclear Material and  

National Nuclear Security Administration (NNSA)

Commercial Products Show Potential to serve as Nuclear Material and Commercial Products Show Potential to serve as Nuclear Material and Activity Monitoring Technologies | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > NNSA Blog > Commercial Products Show Potential to serve as ... Commercial Products Show Potential to serve as Nuclear Material and

253

High-Activity Radioactive Materials Removed From Mexico | National Nuclear  

NLE Websites -- All DOE Office Websites (Extended Search)

High-Activity Radioactive Materials Removed From Mexico | National Nuclear High-Activity Radioactive Materials Removed From Mexico | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Press Releases > High-Activity Radioactive Materials Removed From Mexico Press Release High-Activity Radioactive Materials Removed From Mexico Nov 15, 2013 WASHINGTON, D.C. - The National Nuclear Security Administration (NNSA)

254

Atomic Energy and Nuclear Materials Program (Tennessee) | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Materials Program (Tennessee) Nuclear Materials Program (Tennessee) Atomic Energy and Nuclear Materials Program (Tennessee) < Back Eligibility Commercial Construction Developer General Public/Consumer Industrial Investor-Owned Utility Utility Program Info State Tennessee Program Type Environmental Regulations Siting and Permitting Provider Tennessee Department Of Environment and Conservation The Atomic Energy and Nuclear Materials section of the Tennessee Code covers all of the regulations, licenses, permits, siting requirements, and practices relevant to a nuclear energy development. In addition to the Tennessee Code the Department of Environment and Conservation has a rule pertaining to the licensing and registration of sources of radiation. The Department's rules state that any contractor or subcontractor of the U.S.

255

NNSA: Securing Domestic Radioactive Material | National Nuclear Security  

NLE Websites -- All DOE Office Websites (Extended Search)

NNSA: Securing Domestic Radioactive Material | National Nuclear Security NNSA: Securing Domestic Radioactive Material | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Fact Sheets > NNSA: Securing Domestic Radioactive Material Fact Sheet NNSA: Securing Domestic Radioactive Material Apr 12, 2013 The Department of Energy's National Nuclear Security Administration (NNSA),

256

High-Activity Radioactive Materials Removed From Mexico | National Nuclear  

National Nuclear Security Administration (NNSA)

High-Activity Radioactive Materials Removed From Mexico | National Nuclear High-Activity Radioactive Materials Removed From Mexico | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > Media Room > Press Releases > High-Activity Radioactive Materials Removed From Mexico Press Release High-Activity Radioactive Materials Removed From Mexico Nov 15, 2013 WASHINGTON, D.C. - The National Nuclear Security Administration (NNSA)

257

Damper mechanism for nuclear reactor control elements  

DOE Patents (OSTI)

A damper mechanism which provides a nuclear reactor control element decelerating function at the end of the scram stroke. The total damping function is produced by the combination of two assemblies, which operate in sequence. First, a tapered dashram assembly decelerates the control element to a lower velocity, after which a spring hydraulic damper assembly takes over to complete the final damping.

Taft, William Elwood (Los Gatos, CA)

1976-01-01T23:59:59.000Z

258

Special Topics: Nuclear Materials: Web resources  

Science Conference Proceedings (OSTI)

WEB: U.S.NRC Glossary United States Nuclear Regulatory Commission, 0, 769, Cathy Rohrer, 10/19/2007 2:38 PM by Cathy Rohrer. New Messages, Rating...

259

Fast-acting nuclear reactor control device  

DOE Patents (OSTI)

A fast-acting nuclear reactor control device for moving and positioning a fety control rod to desired positions within the core of the reactor between a run position in which the safety control rod is outside the reactor core, and a shutdown position in which the rod is fully inserted in the reactor core. The device employs a hydraulic pump/motor, an electric gear motor, and solenoid valve to drive the safety control rod into the reactor core through the entire stroke of the safety control rod. An overrunning clutch allows the safety control rod to freely travel toward a safe position in the event of a partial drive system failure.

Kotlyar, Oleg M. (Idaho Falls, ID); West, Phillip B. (Idaho Falls, ID)

1993-01-01T23:59:59.000Z

260

Materials Issues in Nuclear-Waste Management  

Science Conference Proceedings (OSTI)

253 260. 18. R.D. McCright et al., Candidate Container Materials for Yucca ... K.L. Murty and M.D. Mathew, Condition Monitoring of Structural Materials Using ...

Note: This page contains sample records for the topic "nuclear material control" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

Understanding Defect Behavior in Nuclear Energy Materials  

Science Conference Proceedings (OSTI)

About this Abstract. Meeting, Materials Science & Technology 2012. Symposium, International Symposium on Defects, Transport and Related Phenomena.

262

Downhole material injector for lost circulation control  

DOE Patents (OSTI)

Apparatus and method are disclosed for simultaneously and separately emplacing two streams of different materials through a drill string in a borehole to a downhole location for lost circulation control. The two streams are mixed outside the drill string at the desired downhole location and harden only after mixing for control of a lost circulation zone. 6 figs.

Glowka, D.A.

1994-09-06T23:59:59.000Z

263

Downhole material injector for lost circulation control  

DOE Patents (OSTI)

This invention is comprised of an apparatus and method for simultaneously and separately emplacing two streams of different materials through a drillstring in a borehole to a downhole location for lost circulation control. The two streams are mixed outside the drillstring at the desired downhole location and harden only after mixing for control of a lost circulation zone.

Glowka, D.A.

1991-12-31T23:59:59.000Z

264

Downhole material injector for lost circulation control  

DOE Patents (OSTI)

This invention is comprised of an apparatus and method for simultaneously and separately emplacing two streams of different materials through a drillstring in a borehole to a downhole location for lost circulation control. The two streams are mixed outside the drillstring at the desired downhole location and harden only after mixing for control of a lost circulation zone.

Glowka, D.A.

1991-01-01T23:59:59.000Z

265

Downhole material injector for lost circulation control  

DOE Patents (OSTI)

Apparatus and method for simultaneously and separately emplacing two streams of different materials through a drillstring in a borehole to a downhole location for lost circulation control. The two streams are mixed outside the drillstring at the desired downhole location and harden only after mixing for control of a lost circulation zone.

Glowka, David A. (Tijeras, NM)

1994-01-01T23:59:59.000Z

266

Nuclear reactor control apparatus. [FBR  

DOE Patents (OSTI)

Nuclear reactor safety rod release apparatus comprises a ring which carries detents normally positioned in an annular recess in outer side of the rod, the ring being held against the lower end of a drive shaft by magnetic force exerted by a solenoid carried by the drive shaft. When the solenoid is de-energized, the detent-carrying ring drops until the detents contact a cam surface associated with the lower end of the drive shaft, at which point the detents are cammed out of the recess in the safety rod to release the rod from the drive shaft. In preferred embodiments of the invention, an additional latch is provided to release a lower portion of a safety rod under conditions that may interfere with movement of the entire rod.

Sridhar, B.N.

1981-04-16T23:59:59.000Z

267

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

Science Conference Proceedings (OSTI)

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.

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

2004-11-01T23:59:59.000Z

268

Materials Science of Nuclear Waste Management II  

Science Conference Proceedings (OSTI)

Mar 7, 2013 ... Challenges include the multi-phase nature of the materials, galvanic .... to quantify phase volume percentage and pore size distribution data to...

269

Fissile Materials Disposition | National Nuclear Security Administrati...  

NLE Websites -- All DOE Office Websites (Extended Search)

Materials Disposition Since the end of the Cold War, significant quantities of plutonium and highly enriched uranium have become surplus to the defense needs of both the...

270

Material Testing - Nuclear Engineering Division (Argonne)  

NLE Websites -- All DOE Office Websites (Extended Search)

Departments involved: Engineering Development and Applications Irradiated Materials Two hot-cell test facilities are used to develop experimental data on the irradiation-assisted...

271

Materials Challenges in Next Generation Nuclear Reactors  

Science Conference Proceedings (OSTI)

Materials under active consideration for use in different reactor components ... A Theoretical Model of Corrosion Rate Distribution in Liquid LBE Flow Loop at...

272

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

Science Conference Proceedings (OSTI)

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.

None

2009-02-01T23:59:59.000Z

273

Handbook on Neutron Absorber Materials for Spent Nuclear Fuel Applications  

Science Conference Proceedings (OSTI)

This handbook is intended to become a single source of information regarding technical characteristics of neutron absorber materials that have been used for storage and transportation of spent nuclear fuel as well as to provide a summary of users' experience.

2005-12-08T23:59:59.000Z

274

Beryllium - A Unique Material in Nuclear Applications  

SciTech Connect

Beryllium, due to its unique combination of structural, chemical, atomic number, and neutron absorption cross section characteristics, has been used successfully as a neutron reflector for three generations of nuclear test reactors at the Idaho National Engineering and Environmental Laboratory (INEEL). The Advanced Test Reactor (ATR), the largest test reactor in the world, has utilized five successive beryllium neutron reflectors and is scheduled for continued operation with a sixth beryllium reflector. A high radiation environment in a test reactor produces radiation damage and other changes in beryllium. These changes necessitate safety analysis of the beryllium, methods to predict performance, and appropriate surveillances. Other nuclear applications also utilize beryllium. Beryllium, given its unique atomic, physical, and chemical characteristics, is widely used as a window for x-rays and gamma rays. Beryllium, intimately mixed with high-energy alpha radiation emitters has been successfully used to produce neutron sources. This paper addresses operational experience and methodologies associated with the use of beryllium in nuclear test reactors and in windows for x-rays and gamma rays. Other nuclear applications utilizing beryllium are also discussed.

T., A. Tomberlin

2004-11-01T23:59:59.000Z

275

Unclassified Controlled Nuclear Information (UCNI) | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Unclassified Controlled Nuclear Unclassified Controlled Nuclear Information (UCNI) Unclassified Controlled Nuclear Information (UCNI) Welcome to the Unclassified Controlled Nuclear Information (UCNI) webpage. This page is designed to provide information, answer questions, and provide a point of contact for UCNI inquiries. UCNI is certain unclassified information about nuclear facilities and nuclear weapons that must be controlled because its unauthorized release could have a significant adverse effect on the national security or public health and safety. The Director, Office of Classification (OC), decides what specific information is UCNI. For information under the cognizance of the National Nuclear Security Administration (NNSA), the decisions are made in coordination with the Associate Administrator for Defense Nuclear

276

Nuclear Maintenance Applications Center: Foreign Material Exclusion Guidelines  

Science Conference Proceedings (OSTI)

Foreign material exclusion (FME) is vital to the safe and reliable operation of nuclear power plants. The entry of foreign material (FM) into primary or secondary plant systems, equipment, and components can cause equipment degradation or inoperability, lost generation, fuel cladding damage, high radiation, and contamination levels that could spread throughout plant systems; it can also increase operations and maintenance (O&M) costs and adversely impact nuclear safety. The FME program is a plantwide ini...

2008-07-01T23:59:59.000Z

277

Special Nuclear Material Portal Monitoring at the Nevada Test Site  

SciTech Connect

In the past, acceptance and performance testing of the various Special Nuclear Material (SNM) monitoring devices at the Nevada Test Site has been performed by the Radiological Health Instrumentation Department. Calibration and performance tests on the PM-700 personnel portal monitor were performed but there was no test program for the VM-250 vehicle portal monitor because it had never been put into service. The handheld SNM monitors, the TSA model 470B, were being calibrated annually, but there was no program in place to test them quarterly. In April of 2007, the Material Control and Accountability (MC&A) Manager at the time decided that the program needed to be strengthened and MC&A took over performance testing of all SNM portal monitoring equipment. This paper will discuss the following activities associated with creating a performance testing program: changing the culture, learning the systems, writing procedures, troubleshooting/repairing, validating the process, control of equipment, acquisition of new systems, and running the program.

Mike Murphy

2008-03-01T23:59:59.000Z

278

Special Nuclear Material Control Program Training Objectives  

National Nuclear Security Administration (NNSA)

concerns - deregulation impacts, capital costs of maintaining large inventories, O&M costs for monitoring & performing inventories, & operating schedule adherence Why Was ANSI...

279

GTRI's Nuclear and Radiological Material Protection | National...  

National Nuclear Security Administration (NNSA)

of national regulatory infrastructures; Provide remote monitoring and orphan source search and recovery capabilities to support national efforts to strengthen the control and...

280

Advanced nuclear plant control room complex  

DOE Patents (OSTI)

An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

Scarola, Kenneth (Windsor, CT); Jamison, David S. (Windsor, CT); Manazir, Richard M. (North Canton, CT); Rescorl, Robert L. (Vernon, CT); Harmon, Daryl L. (Enfield, CT)

1993-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear material control" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

Alarm system for a nuclear control complex  

DOE Patents (OSTI)

An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

Scarola, Kenneth (Windsor, CT); Jamison, David S. (Windsor, CT); Manazir, Richard M. (North Canton, CT); Rescorl, Robert L. (Vernon, CT); Harmon, Daryl L. (Enfield, CT)

1994-01-01T23:59:59.000Z

282

Console for a nuclear control complex  

DOE Patents (OSTI)

An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

Scarola, Kenneth (Windsor, CT); Jamison, David S. (Windsor, CT); Manazir, Richard M. (North Canton, CT); Rescorl, Robert L. (Vernon, CT); Harmon, Daryl L. (Enfield, CT)

1993-01-01T23:59:59.000Z

283

Clearance Levels For Redundant Material From Decommissioning Of Nuclear Facilities  

E-Print Network (OSTI)

Currently, a great deal is happening in the regulatory field regarding the release of radiologically contaminated material: . The IAEA is working on the revision of Safety Series 89 (governing the principles of exemption and clearance) and of the TECDOC 855 on clearance levels. . The European Commission Directive on basic safety standards for protection against ionizing radiation in both nuclear and non-nuclear industries will become effective in May 2000. . The U.S. NRC has issued its draft on clearance of material from nuclear facilities (NUREG 1640), as well as an "issues" paper on the release of solid materials. The U.S. State Department has launched an International Radioactive Source Management Initiative, one of the objectives being to "develop international standards and guidelines and `harmonize' U.S. and IAEA radioactive clearance levels." Of great significance to the implementor of clearance regulations in the nuclear industry is the emergence of the NORM issue durin...

Shankar Menon Program; Shankar Menon

2000-01-01T23:59:59.000Z

284

Resource Letter PSNAC-1: Physics and society: Nuclear arms control  

Science Conference Proceedings (OSTI)

This Resource Letter provides a guide to the literature on nuclear arms control for the nonspecialist. Journal articles and books are cited for the following topics: nuclear weapons

Alexander Glaser; Zia Mian

2008-01-01T23:59:59.000Z

285

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

NLE Websites -- All DOE Office Websites (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...

286

Detecting fission from special nuclear material sources  

DOE Patents (OSTI)

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.

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

2012-06-05T23:59:59.000Z

287

Thermal Analysis of Storage Cans Containing Special Nuclear Materials  

Science Conference Proceedings (OSTI)

A series of thermal analyses have been completed for ten storage can configurations representing various cases of materials stored in F-Area. The analyses determine the temperatures of the cans, the special nuclear material, and the air sealed within the cans. Analyses to aid in understanding the effect of oxide accumulation and metal aging on temperatures are also included.

Jerrell, J.W.

2000-11-17T23:59:59.000Z

288

Nuclear Energy Enabling Technologies (NEET) Reactor Materials  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Enabling Technologies (NEET) Reactor Materials Enabling Technologies (NEET) Reactor Materials Award Recipient Estimated Award Amount* Award Location Supporting Organizations Project Description University of Nebraska $979,978 Lincoln, NE Massachusetts Institute of Technology (Cambridge, MA), Texas A&M (College Station, TX) Project will explore the development of advanced metal/ceramic composites. These improvements could lead to more efficient production of electricity in advanced reactors. Oak Ridge National Laboratory $849,000 Oak Ridge, TN University of Wisconsin-Madison (Madison, WI) Project will develop novel high-temperature high-strength steels with the help of computational modeling, which could lead to increased efficiency in advanced reactors. Pacific Northwest National Laboratory

289

The U.S. national nuclear forensics library, nuclear materials information program, and data dictionary  

Science Conference Proceedings (OSTI)

Nuclear forensics assessments to determine material process history requires careful comparison of sample data to both measured and modeled nuclear material characteristics. Developing centralized databases, or nuclear forensics libraries, to house this information is an important step to ensure all relevant data will be available for comparison during a nuclear forensics analysis and help expedite the assessment of material history. The approach most widely accepted by the international community at this time is the implementation of National Nuclear Forensics libraries, which would be developed and maintained by individual nations. This is an attractive alternative toan international database since it provides an understanding that each country has data on materials produced and stored within their borders, but eliminates the need to reveal any proprietary or sensitive information to other nations. To support the concept of National Nuclear Forensics libraries, the United States Department of Energy has developed a model library, based on a data dictionary, or set of parameters designed to capture all nuclear forensic relevant information about a nuclear material. Specifically, information includes material identification, collection background and current location, analytical laboratories where measurements were made, material packaging and container descriptions, physical characteristics including mass and dimensions, chemical and isotopic characteristics, particle morphology or metallurgical properties, process history including facilities, and measurement quality assurance information. While not necessarily required, it may also be valuable to store modeled data sets including reactor burn-up or enrichment cascade data for comparison. It is fully expected that only a subset of this information is available or relevant to many materials, and much of the data populating a National Nuclear Forensics library would be process analytical or material accountability measurement data as opposed to a complete forensic analysis of each material in the library.

Lamont, Stephen Philip [Los Alamos National Laboratory; Brisson, Marcia [DOE-IN; Curry, Michael [DEPT. OF STATE

2011-02-17T23:59:59.000Z

290

Insider Threat - Material Control and Accountability Mitigation (Presentation)  

SciTech Connect

Why is the insider a concern? There are many documented cases of nuclear material available for sale - there are more insider diversions than outsider attacks and more than 18 documented cases of theft or loss of plutonium or highly enriched uranium. Insider attributes are: have access, has authority, possesses knowledge, works with absence of timeline, can test system, and may act alone or support a team. Material control and accountability (MC&A) is an essential part of an integrated safeguards system. Objectives of MC&A are: (1) Ongoing confirmation of the presence of special nuclear material (SNM) in assigned locations; (2) Prompt investigation of anomalies that may indicate a loss of SNM; (3) Timely and localized detection of loss, diversion, or theft of a goal quantity; (4) Rapid assessment and response to detection alarms; and (5) Timely generation of information to aid in the recovery of SNM in the event of an actual loss, diversion, or theft from the purview of the MC&A system. Control and accountability of material, equipment, and data are essential to minimizing insider threats.

Powell, Danny H [ORNL; Elwood Jr, Robert H [ORNL

2011-01-01T23:59:59.000Z

291

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

Science Conference Proceedings (OSTI)

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.

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

2010-01-01T23:59:59.000Z

292

Fast-acting nuclear reactor control device  

DOE Patents (OSTI)

This invention consists of a fast-acting nuclear reactor control device for moving and positioning a safety control rod to desired elevations within the core of the reactor between a run position in which the safety control rod is outside the reactor core, and a shutdown position in which the rod is fully inserted in the reactor core. The device employs a hydraulic pump motor, an electric gear motor, and a solenoid valve to drive the safety control rod into the reactor core through the entire stroke of the safety control rod. An overrunning clutch, allows the safety control rod to freely travel toward a safe position in the event of a partial drive system failure.

Kotlyar, O.M.; West, P.B.

1992-12-31T23:59:59.000Z

293

Nuclear engine flow reactivity shim control  

DOE Patents (OSTI)

A nuclear engine control system is provided which automatically compensates for reactor reactivity uncertainties at the start of life and reactivity losses due to core corrosion during the reactor life in gas-cooled reactors. The coolant gas flow is varied automatically by means of specially provided control apparatus so that the reactor control drums maintain a predetermined steady state position throughout the reactor life. This permits the reactor to be designed for a constant drum position and results in a desirable, relatively flat temperature profile across the core. (Official Gazette)

Walsh, J.M.

1973-12-11T23:59:59.000Z

294

Nuclear Maintenance Applications Center: Material Handling Application Guide  

Science Conference Proceedings (OSTI)

BackgroundDuring 2005 and 2006, there were nine Institute of Nuclear Power Operations (INPO) operating events (OEs) from material handling incidents. A fatality occurred at Browns Ferry on Oct. 1, 2005, when a small article radiation monitor overturned while being moved on a material handling cart (INPO OE21844).More than 50 serious OEs concerning material handling activities have occurred in the past 10 years. The majority of these incidents involved the ...

2012-09-28T23:59:59.000Z

295

Material's Properties Control by Nano-Scale Surface Functionalization...  

NLE Websites -- All DOE Office Websites (Extended Search)

Material's Properties Control by Nano-Scale Surface Functionalization Material's Properties Control by Nano-Scale Surface Functionalization Theme We aim at developing an original...

296

Graphite matrix materials for nuclear waste isolation  

SciTech Connect

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.

Morgan, W.C.

1981-06-01T23:59:59.000Z

297

Optoelectronic inventory system for special nuclear material  

SciTech Connect

In support of the Department of Energy`s Dismantlement Program, the Optoelectronics Characterization and Sensor Development Department 2231 at Sandia National Laboratories/New Mexico has developed an in situ nonintrusive Optoelectronic Inventory System (OIS) that has the potential for application wherever periodic inventory of selected material is desired. Using a network of fiber-optic links, the OIS retrieves and stores inventory signatures from data storage devices (which are permanently attached to material storage containers) while inherently providing electromagnetic pulse immunity and electrical noise isolation. Photovoltaic cells (located within the storage facility) convert laser diode optic power from a laser driver to electrical energy. When powered and triggered, the data storage devices sequentially output their digital inventory signatures through light-emitting diode/photo diode data links for retrieval and storage in a mobile data acquisition system. An item`s exact location is determined through fiber-optic network and software design. The OIS provides an on-demand method for obtaining acceptable inventory reports while eliminating the need for human presence inside the material storage facility. By using modularization and prefabricated construction with mature technologies and components, an OIS installation with virtually unlimited capacity can be tailored to the customer`s requirements.

Sieradzki, F.H.

1994-01-01T23:59:59.000Z

298

DOE O 452.4B, Security and Use Control of Nuclear Explosives and Nuclear Weapons  

Directives, Delegations, and Requirements

This Order establishes requirements to implement the nuclear explosive security and use control elements of DOE O 452.1D, Nuclear Explosive and Weapon Surety ...

2010-01-22T23:59:59.000Z

299

Materials Modeling and Simulation for Nuclear Fuels (MMSNF) Workshops  

NLE Websites -- All DOE Office Websites (Extended Search)

Aerial photo of Argonne National Laboratory Argonne National Laboratory University of Chicago Chicago Photography courtesy Thomas F Ewing Privacy and Security Notice The MMSNF Workshops The goal of the Materials Modeling and Simulation for Nuclear Fuels (MMSNF) workshops is to stimulate research and discussions on modeling and simulations of nuclear fuels, to assist the design of improved fuels and the evaluation of fuel performance. In addition to research focused on existing or improved types of LWR reactors, recent modeling programs, networks, and links have been created to develop innovative nuclear fuels and materials for future generations of nuclear reactors. Examples can be found in Europe (e.g. F-BRIDGE project and ACTINET network and SAMANTHA cooperative network), in the USA (e.g. CASL, NEAMS, CESAR and CMSN network

300

Application of a Hybrid Potts-Phase Field Model to Nuclear Materials  

Science Conference Proceedings (OSTI)

About this Abstract. Meeting, Materials Science & Technology 2012. Symposium, Materials Development for Nuclear Applications and Extreme Environments.

Note: This page contains sample records for the topic "nuclear material control" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

Low Activation Materials for Nuclear-Grade Joining of SiC ...  

Science Conference Proceedings (OSTI)

About this Abstract. Meeting, Materials Science & Technology 2012. Symposium, Materials Development for Nuclear Applications and Extreme Environments.

302

A Path Forward to Advanced Nuclear Fuels: Spectroscopic Calorimetry of Nuclear Fuel Materials  

SciTech Connect

The goal is to relieve the shortage of thermodynamic and kinetic information concerning the stability of nuclear fuel alloys. Past studies of the ternary nuclear fuel UPuZr have demonstrated constituent redistribution when irradiated or with thermal treatment. Thermodynamic data is key to predicting the possibilities of effects such as constituent redistribution within the fuel rods and interaction with cladding materials.

Tobin, J G

2009-02-10T23:59:59.000Z

303

Control rod for a nuclear reactor  

DOE Patents (OSTI)

A control rod assembly for a nuclear reactor is disclosed having a remotely disengageable coupling between the control rod and the control rod drive shaft. The coupling is actuated by first lowering then raising the drive shaft. The described motion causes axial repositioning of a pin in a grooved rotatable cylinder, each being attached to different parts of the drive shaft which are axially movable relative to each other. In one embodiment, the relative axial motion of the parts of the drive shaft is used either to couple or to uncouple the connection by forcing resilient members attached to the drive shaft into or out of shouldered engagement, respectively, with an indentation formed in the control rod.

Roman, Walter G. (Pittsburgh, PA); Sutton, Jr., Harry G. (Pittsburgh, PA)

1979-01-01T23:59:59.000Z

304

Systems/Process Monitoring, Diagnostics and Control - Nuclear Engineering  

NLE Websites -- All DOE Office Websites (Extended Search)

Capabilities > Nuclear Systems Capabilities > Nuclear Systems Technologies > Systems/Process Monitoring, Diagnostics and Control Capabilities Nuclear Systems Technologies Nuclear Criticality Safety Research Reactor Analysis Decontamination and Decommissioning Systems/Process Monitoring, Diagnostics and Control Overview Process Monitoring & Signal Validation Diagnostic & Advisory Systems Advanced (AI-based) Nonlinear Controllers for Industrial Processes Artificial intelligence Other Capabilities Work with Argonne Contact us For Employees Site Map Help Systems/Process Monitoring, Diagnostics and Control Bookmark and Share Systems/Process Monitoring, Diagnostics and Control Systems/Process Monitoring, Diagnostics and Control. Click on image to view larger image. The goal of the Nuclear Engineering Division's research on advanced

305

IMPACT OF NUCLEAR MATERIAL DISSOLUTION ON VESSEL CORROSION  

Science Conference Proceedings (OSTI)

Different nuclear materials require different processing conditions. In order to maximize the dissolver vessel lifetime, corrosion testing was conducted for a range of chemistries and temperature used in fuel dissolution. Compositional ranges of elements regularly in the dissolver were evaluated for corrosion of 304L, the material of construction. Corrosion rates of AISI Type 304 stainless steel coupons, both welded and non-welded coupons, were calculated from measured weight losses and post-test concentrations of soluble Fe, Cr and Ni.

Mickalonis, J.; Dunn, K.; Clifton, B.

2012-10-01T23:59:59.000Z

306

Chemical digestion of low level nuclear solid waste material  

DOE Patents (OSTI)

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.

Cooley, Carl R. (Richland, WA); Lerch, Ronald E. (Richland, WA)

1976-01-01T23:59:59.000Z

307

Nuclear Resonant Scattering on Earth Materials using Synchrotron Radiation  

NLE Websites -- All DOE Office Websites (Extended Search)

NRS2005 Home NRS2005 Home Agenda Organizing Committee Nuclear Resonant Scattering on Earth Materials using Synchrotron Radiation February 12-13, 2005 Advanced Photon Source Argonne National Laboratory - Argonne, Illinois, USA Nuclear Resonant Scattering (NRS) techniques provide the Earth and planetary science community with opportunities for new and exciting results on the properties of materials at high pressure and temperature conditions. Such NRS experiments have become possible due to the extreme brightness of third-generation synchrotron radiation sources. NRS techniques fall into two broad areas, which are in many ways ideally or even uniquely suited for addressing a number of important geophysical questions: Nuclear Resonant Inelastic X-ray Scattering (NRIXS) provides information on

308

Pulsed Photofission Delayed Gamma Ray Detection for Nuclear Material Identification  

SciTech Connect

Innovative systems with increased sensitivity and resolution are in great demand to detect diversion and to prevent misuse in support of nuclear materials management for the U.S. fuel cycle. Nuclear fission is the most important multiplicative process involved in non-destructive active interrogation. This process produces the most easily recognizable signature for nuclear materials. High-energy gamma rays can also excite a nucleus and cause fission through a process known as photofission. After photofission reactions, delayed signals are easily distinguishable from the interrogating radiation. Linac-based, advanced inspection techniques utilizing the fission signals after photofission have been extensively studied for homeland security applications. Previous research also showed that a unique delayed gamma ray energy spectrum exists for each fissionable isotope. Isotopic composition measurement methods based on delayed gamma ray spectroscopy will be the primary focus of this work.

John Kavouras; Xianfei Wen; Daren R. Norman; Dante R. Nakazawa; Haori Yang

2012-11-01T23:59:59.000Z

309

Adhesion layer for etching of tracks in nuclear trackable materials  

DOE Patents (OSTI)

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.

Morse, Jeffrey D. (Martinez, CA); Contolini, Robert J. (Lake Oswego, OR)

2001-01-01T23:59:59.000Z

310

Storage of nuclear materials by encapsulation in fullerenes  

DOE Patents (OSTI)

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.

Coppa, Nicholas V. (Los Alamos, NM)

1994-01-01T23:59:59.000Z

311

International Export Control Cooperation | National Nuclear Security...  

National Nuclear Security Administration (NNSA)

Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

312

Nuclear reactor shutdown control rod assembly  

DOE Patents (OSTI)

A temperature responsive, self-actuated nuclear reactor shutdown control rod assembly 10. The upper end 18 of a lower drive line 17 fits within the lower end of an upper drive line 12. The lower end (not shown) of the lower drive line 17 is connected to a neutron absorber. During normal temperature conditions the lower drive line 17 is supported by detent means 22,26. When an overtemperature condition occurs thermal actuation means 34 urges ring 26 upwardly sufficiently to allow balls 22 to move radially outwardly thereby allowing lower drive line 17 to move downwardly toward the core of the nuclear reactor resulting in automatic reduction of the reactor powder.

Bilibin, Konstantin (North Hollywood, CA)

1988-01-01T23:59:59.000Z

313

ADVANCED CERAMIC MATERIALS FOR NEXT-GENERATION NUCLEAR APPLICATIONS  

SciTech Connect

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.

Marra, J.

2010-09-29T23:59:59.000Z

314

Nuclear Material Processing at the Savannah River Site  

Science Conference Proceedings (OSTI)

Plutonium production for national defense began at Savannah River in the mid-1950s, following construction of production reactors and separations facilities. Following the successful completion of its production mission, the site`s nuclear material processing facilities continue to operate to perform stabilization of excess materials and potentially support the disposition of these materials. A number of restoration and productivity improvement projects implemented in the 1980s, totaling nearly a billion dollars, have resulted in these facilities representing the most modern and only remaining operating large-scale processing facilities in the DOE Complex. Together with the Site`s extensive nuclear infrastructure, and integrated waste management system, SRS is the only DOE site with the capability and mission of ongoing processing operations.

Severynse, T.F. [Westinghouse Savannah River Company, AIKEN, SC (United States)

1998-07-01T23:59:59.000Z

315

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

SciTech Connect

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.

Powell, Danny H [ORNL; Jensen, Bruce A [ORNL

2011-01-01T23:59:59.000Z

316

Apparatus for controlling nuclear core debris  

DOE Patents (OSTI)

Nuclear reactor apparatus for containing, cooling, and dispersing reactor debris assumed to flow from the core area in the unlikely event of an accident causing core meltdown. The apparatus includes a plurality of horizontally disposed vertically spaced plates, having depressions to contain debris in controlled amounts, and a plurality of holes therein which provide natural circulation cooling and a path for debris to continue flowing downward to the plate beneath. The uppermost plates may also include generally vertical sections which form annular-like flow areas which assist the natural circulation cooling.

Jones, Robert D. (Irwin, PA)

1978-01-01T23:59:59.000Z

317

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

SciTech Connect

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.

Magoulas, V.

2013-06-03T23:59:59.000Z

318

Materials characterization center workshop on compositional and microstructural analysis of nuclear waste materials. Summary report  

SciTech Connect

The purpose of the Workshop on Compositional and Microstructural Analysis of Nuclear Waste Materials, conducted November 11 and 12, 1980, was to critically examine and evaluate the various methods currently used to study non-radioactive, simulated, nuclear waste-form performance. Workshop participants recognized that most of the Materials Characterization Center (MCC) test data for inclusion in the Nuclear Waste Materials Handbook will result from application of appropriate analytical procedures to waste-package materials or to the products of performance tests. Therefore, the analytical methods must be reliable and of known accuracy and precision, and results must be directly comparable with those from other laboratories and from other nuclear waste materials. The 41 participants representing 18 laboratories in the United States and Canada were organized into three working groups: Analysis of Liquids and Solutions, Quantitative Analysis of Solids, and Phase and Microstructure Analysis. Each group identified the analytical methods favored by their respective laboratories, discussed areas needing attention, listed standards and reference materials currently used, and recommended means of verifying interlaboratory comparability of data. The major conclusions from this workshop are presented.

Daniel, J.L.; Strachan, D.M.; Shade, J.W.; Thomas, M.T.

1981-06-01T23:59:59.000Z

319

Material Protection, Control and Accounting program (MPC&A) | National  

NLE Websites -- All DOE Office Websites (Extended Search)

Protection, Control and Accounting program (MPC&A) | National Protection, Control and Accounting program (MPC&A) | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Material Protection, Control and Accounting program (MPC&A) Home > About Us > Our Programs > Nonproliferation > International Materials Protection and Cooperation > Material Protection, Control and Accounting

320

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

Science Conference Proceedings (OSTI)

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.

NONE

1995-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear material control" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

Nuclear Power Advisory Meeting: Instrumentation and Control Briefing Book  

Science Conference Proceedings (OSTI)

This document combines the material previously included in the Instrumentation and Control (I&C) Briefing Book for the Nuclear Power Advisory Meeting with the annual I&C research plan, replacing the latter document. It contains key information on the program and its projects including: 1. Program executive summary a high level document on the key activities of the I&C base program as well as its three supplemental groups 2. A consolidated list of EPRI I&C program deliverables for the next three years 3. ...

2011-08-18T23:59:59.000Z

322

Material handling for the Los Alamos National Laboratory Nuclear Material Storage Facility  

SciTech Connect

This paper will present the design and application of material handling and automation systems currently being developed for the Los Alamos National Laboratory (LANL) Nuclear Material Storage Facility (NMSF) renovation project. The NMSF is a long-term storage facility for nuclear material in various forms. The material is stored within tubes in a rack called a basket. The material handling equipment range from simple lift assist devices to more sophisticated fully automated robots, and are split into three basic systems: a Vault Automation System, an NDA automation System, and a Drum handling System. The Vault Automation system provides a mechanism to handle a basket of material cans and to load/unload storage tubes within the material vault. In addition, another robot is provided to load/unload material cans within the baskets. The NDA Automation System provides a mechanism to move material within the small canister NDA laboratory and to load/unload the NDA instruments. The Drum Handling System consists of a series of off the shelf components used to assist in lifting heavy objects such as pallets of material or drums and barrels.

Pittman, P.; Roybal, J.; Durrer, R.; Gordon, D.

1999-04-01T23:59:59.000Z

323

Approach for enhancing nuclear materials tracking and reporting in waste  

SciTech Connect

Recent policy from the Department of Energy/Office of Safeguards and Security (DOE/OSS) has identified the need to report nuclear materials in waste in a manner that is consistent with the Department of Energy's Nuclear Materials Information System (NMIS), which uses Form 471 as its official record. NMIS is used to track nuclear material inventories while they are subject to safeguards. This requirement necessitates the reevaluation of existing business practices that are used to track and report these nuclear materials. This paper provides a methodology for applying a systems approach to the evaluation of the flow of nuclear waste materials from a generating facility through to permanent disposal. This methodology can be used to integrate existing systems and leverage data already gathered that support both the waste reporting requirements and the NMIS requirements. In order to consider an active waste reporting system that covers waste management through to final disposal, the requirements for characterization, certification, and transportation for disposal at the Waste Isolation Pilot Plant (WIPP) are used as an example. These requirements are found in the WIPP Waste Acceptance Criteria (WIPP/WAC) and associated requirement documents. This approach will prevent inconsistencies in reported data and address current and future needs. For example, spent fuel (which the U.S. intends to dispose of as high-level waste) has not been viewed as particularly attractive in terms of proliferation in comparison to materials associated with other parts of the nuclear fuel cycle. However, collecting high-level waste (or some types of defense waste) in one location where it will be left for hundreds or thousands of years presents proliferation and safeguards issues that need to be considered as part of a systems evaluation. This paper brings together information on domestic and international safeguards practices and considers the current system of documentation used by the U.S. Department of Energy for radioactive waste disposal. The information presented represents current practices, and we recognize that the practices were designed to address different goals. After providing an overview of these areas, some steps that may help develop safeguards systems for geologic repositories in the U.S. context are discussed.

Longmire, V. L. (Victoria L.); Seitz, S. L. (Sharon L.); Sinkule, B. J. (Barbara J.)

2001-06-01T23:59:59.000Z

324

97 percent of special nuclear material de-inventoried from LLNL...  

NLE Websites -- All DOE Office Websites (Extended Search)

97 percent of special nuclear material de-inventoried from LLNL | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the...

325

Basic science research to support the nuclear material focus area  

SciTech Connect

The Department of Energy's (DOE'S) Office of Environmental Management (EM) is responsible for managing more than 760,000 metric tons of nuclear material that is excess to the current DOE weapons program, as a result of shutdown of elements of the weapons program, mainly during the 1990s. EMowned excess nuclear material comprises a variety of material types, including uranium, plutonium, other actinides and other radioactive elements in numerous forms, all of which must be stabilized for storage and ultimate disposition. Much of this quantity has been in storage for many years. Shutdown of DOE sites and facilities requires removal of nuclear material and consolidation at other sites, and may be delayed by the lack of available technology. Within EM, the Office of Science and Technology (OST) is dedicated to providing timely, relevant technology to accelerate completion and reduce cleanup cost of the DOE environmental legacy. OST is organized around five focus areas, addressing crucial areas of end-user-defined technology need. The Focus Areas regularly identify potential technical solutions for which basic scientific research is needed to determine if the technical solution can be developed and deployed. To achieve a portfolio of projects that is balanced between near-term priorities driven by programmatic risks (such as site closure milestones) and long-term, high-consequence needs that depend on extensive research and development, OST has established the Environmental Management Science Program (EMSP) to develop the scientific basis for solutions to long-term site needs. The EMSP directs calls for proposals to address scientific needs of the focus areas. Needs are identified and validated annually by individual sites in workshops conducted across the complex. The process captures scope and schedule requirements of the sites, so that focus areas can identify technology that can be delivered to sites in time to complete site cleanup. The Nuclear Material Focus Area (NMFA) has identified over two hundred science and technology needs, of which more than thirty are science needs.

Boak, J. M. (Jeremy M.); Eller, P. Gary; Chipman, N. A.; Castle, P. M.

2002-01-01T23:59:59.000Z

326

Basic Science Research to Support the Nuclear Materials Focus Area  

SciTech Connect

The Department of Energy's (DOE's) Office of Environmental Management (EM) is responsible for managing more than 760,000 metric tons of nuclear material that is excess to the current DOE weapons program, as a result of shutdown of elements of the weapons program, mainly during the 1990s. EMowned excess nuclear material comprises a variety of material types, including uranium, plutonium, other actinides and other radioactive elements in numerous forms, all of which must be stabilized for storage and ultimate disposition. Much of this quantity has been in storage for many years. Shutdown of DOE sites and facilities requires removal of nuclear material and consolidation at other sites, and may be delayed by the lack of available technology. Within EM, the Office of Science and Technology (OST) is dedicated to providing timely, relevant technology to accelerate completion and reduce cleanup cost of the DOE environmental legacy. OST is organized around five focus areas, addressing crucial areas of end-user-defined technology need. The Focus Areas regularly identify potential technical solutions for which basic scientific research is needed to determine if the technical solution can be developed and deployed. To achieve a portfolio of projects that is balanced between near-term priorities driven by programmatic risks (such as site closure milestones) and long-term, high-consequence needs that depend on extensive research and development, OST has established the Environmental Management Science Program (EMSP) to develop the scientific basis for solutions to long-term site needs. The EMSP directs calls for proposals to address scientific needs of the focus areas. Needs are identified and validated annually by individual sites in workshops conducted across the complex. The process captures scope and schedule requirements of the sites, so that focus areas can identify technology that can be delivered to sites in time to complete site cleanup. The Nuclear Material Focus Area (NMFA) has identified over two hundred science and technology needs, of which more than thirty are science needs.

Chipman, N. A.; Castle, P. M.; Boak, J. M.; Eller, P. G.

2002-02-26T23:59:59.000Z

327

Materials for Nuclear Power: Digital Resource Center -- Articles and ...  

Science Conference Proceedings (OSTI)

... Trends in Nuclear Power, The Nuclear Fuel Cycle, Nuclear Science, Nuclear Engineering ... BOOK: Safety Related Issues of Spent Nuclear Fuel Storage ... A compilation of reports prepared by the Center for Nuclear Waste Regulatory...

328

Photofission-Based, Nuclear Material Detection: Technology Demonstration  

SciTech Connect

The Idaho National Engineering and Environmental Laboratory (INEEL), the Los Alamos National Laboratory (LANL), and the Advanced Research and Applications Corporation (ARACOR) [Sunnyvale, California] performed a photonuclear technology demonstration for shielded nuclear material detection during August 2122, 2002, at the LANL TA-18 facility. The demonstration used the Pulsed Photonuclear Assessment Technique (PPAT) that focused on the application of a photofission-based, nuclear material detection method as a viable complement to the ARACOR Eagle inspection platform. The Eagle is a mobile and fully operational truck and cargo inspection system that uses a 6-MeV electron accelerator to perform real-time radiography. This imaging is performed using an approved radiation-safe or cabinet safe operation relative to the operators, inspectors, and any stowaways within the inspected vehicles. While the PPAT has been primarily developed for active interrogation, its neutron detection system also maintains a complete and effective passive detection capability.

Jones, James Litton; Yoon, Woo Yong; Haskell, Kevin James; Norman, Daren Reeve; Moss, C. E.; Goulding, C. A.; Hollas, C. L.; Myers, W. L.; Franco, Ed

2002-12-01T23:59:59.000Z

329

Nuclear Materials Focus Area Fiscal Year 2002 Mid Year Review  

SciTech Connect

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).

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

2002-05-30T23:59:59.000Z

330

Nuclear Materials Focus Area Fiscal Year 2002 Mid Year Review  

Science Conference Proceedings (OSTI)

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).

Thiel, Elizabeth Chilcote

2002-05-01T23:59:59.000Z

331

Publications [Corrosion and Mechanics of Materials] - Nuclear Engineering  

NLE Websites -- All DOE Office Websites (Extended Search)

Publications Publications Capabilities Materials Testing Environmentally Assisted Cracking (EAC) of Reactor Materials Corrosion Performance/Metal Dusting Overview Light Water Reactors Fossil Energy Fusion Energy Metal Dusting Publications List Irradiated Materials Steam Generator Tube Integrity Other Facilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Corrosion and Mechanics of Materials Selection of Publications Bookmark and Share Journal Articles Manufacturing of representative axial stress corrosion cracks in tube specimens for eddy current testing C.B. Bahn, S. Bakhtiari, J.Y. Park, S. Majumdar Nuclear Engineering and Design, Volume 256, March 2013, Pages 38-44 Leak behavior of steam generator tube-to-tubesheet joints under

332

Neutron Correlations in Special Nuclear Materials, Experiments and Simulations  

SciTech Connect

Fissile materials emit neutrons with an unmistakable signature that can reveal characteristics of the material. We describe here measurements, simulations, and predicted signals expected and prospects for application of neutron correlation measurement methods to detection of special nuclear materials (SNM). The occurrence of fission chains in SNM can give rise to this distinctive, measurable time correlation signal. The neutron signals can be analyzed to detect the presence and to infer attributes of the SNM and surrounding materials. For instance, it is possible to infer attributes of an assembly containing a few kilograms of uranium, purely passively, using detectors of modest size in a reasonable time. Neutron signals of three radioactive sources are shown to illustrate the neutron correlation and analysis method. Measurements are compared with Monte Carlo calculations of the authenticated sources.

Verbeke, J; Dougan, A; Nakae, L; Sale, K; Snyderman, N

2007-06-05T23:59:59.000Z

333

Interactive image quantification tools in nuclear material forensics  

Science Conference Proceedings (OSTI)

Morphological and microstructural features visible in microscopy images of nuclear materials can give information about the processing history of a nuclear material. Extraction of these attributes currently requires a subject matter expert in both microscopy and nuclear material production processes, and is a time consuming, and at least partially manual task, often involving multiple software applications. One of the primary goals of computer vision is to find ways to extract and encode domain knowledge associated with imagery so that parts of this process can be automated. In this paper we describe a user-in-the-loop approach to the problem which attempts to both improve the efficiency of domain experts during image quantification as well as capture their domain knowledge over time. This is accomplished through a sophisticated user-monitoring system that accumulates user-computer interactions as users exploit their imagery. We provide a detailed discussion of the interactive feature extraction and segmentation tools we have developed and describe our initial results in exploiting the recorded user-computer interactions to improve user productivity over time.

Porter, Reid B [Los Alamos National Laboratory; Ruggiero, Christy [Los Alamos National Laboratory; Hush, Don [Los Alamos National Laboratory; Harvey, Neal [Los Alamos National Laboratory; Kelly, Pat [Los Alamos National Laboratory; Scoggins, Wayne [Los Alamos National Laboratory; Tandon, Lav [Los Alamos National Laboratory

2011-01-03T23:59:59.000Z

334

Los Alamos National Laboratory standard nuclear material container  

Science Conference Proceedings (OSTI)

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.

Stone, Timothy A [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

335

Pre-validation of nuclear power plant control room design  

Science Conference Proceedings (OSTI)

Evaluation of the design of complex automation and control room systems is an essential phase in the design process in the nuclear field. For example, in order to meet the nuclear regulatory requirements, the new control room systems have to be evaluated ... Keywords: concept of operations, control room, pre-validation, verification & validation

Jari Laarni; Paula Savioja; Hannu Karvonen; Leena Norros

2011-07-01T23:59:59.000Z

336

REQUIREMENTS FOR RAW MATERIALS IN AN EXPANDING NUCLEAR POWER ECONOMY  

SciTech Connect

The need for breeding does not appear to be highly cost for a moderately optimistic expanding nuclear power economy between 1960 and 2000. Since the expansion rate of the US nuclear economy is assumed to be high at least 2/3 of the U-235 recovered from natural uranium is used to supply reactor inventory. It is the remaining 1/3 of the available U-235 that can be saved by breeder breeders or a breeder and converter are the doubling time and a parameter expressing the total fissile inventory per magawatt of electricity. In fact, the need for new raw material in any given year is reduced more by specific power than by changing from a converter to a value of total inventory per magawatt of electricity and the content and value of plutonium or U-233 than on raw material cost. The use of 12% vs. 4% annual lease charge can change the inventory costs more significantly than either the Pu (or U-233)/U-235 value ratio or raw material cost. Net fuel burn costs vary more with the product of net conversion ratio and Pu (or U-233)/U-235 value ratio than with the cost of raw material. (auth)

Arnold, E.D.; Ullmann, J.W.

1959-01-20T23:59:59.000Z

337

DOE O 452.8, Control of Nuclear Weapon Data  

Directives, Delegations, and Requirements

The directive establishes the policy, process and procedures for control of nuclear weapon data to ensure that dissemination of the information is restricted ...

2011-07-21T23:59:59.000Z

338

Louisiana Nuclear Energy and Radiation Control Law (Louisiana)  

Energy.gov (U.S. Department of Energy (DOE))

The Louisiana Department of Environmental Quality is responsible for the regulation of nuclear energy safety, permitting and radiation safety and control in Louisiana. The Department operates...

339

MANAGING MODERNIZATION OF NUCLEAR POWER PLANT INSTRUMENTATION AND CONTROL SYSTEMS  

E-Print Network (OSTI)

Managing modernization of nuclear power plant instrumentation and control systems February 2004The originating Section of this publication in the IAEA was:

unknown authors

2003-01-01T23:59:59.000Z

340

CORROSION OF LEAD SHIELDING IN NUCLEAR MATERIALS PACKAGES  

SciTech Connect

Inspection of United States-Department of Energy (US-DOE) model 9975 nuclear materials shipping package revealed corrosion of the lead shielding that was induced by off-gas constituents from organic components in the package. Experiments were performed to determine the corrosion rate of lead when exposed to off-gas or degradation products of these organic materials. The results showed that the room temperature vulcanizing (RTV) sealant was the most corrosive organic species used in the construction of the packaging, followed by polyvinyl acetate (PVAc) glue. Fiberboard material, also used in the construction of the packaging induced corrosion to a much lesser extent than the PVAc glue and RTV sealant, and only in the presence of condensed water. The results indicated faster corrosion at temperatures higher than ambient and with condensed water. In light of these corrosion mechanisms, the lead shielding was sheathed in a stainless steel liner to mitigate against corrosion.

Subramanian, K; Kerry Dunn, K; Joseph Murphy, J

2008-07-18T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear material control" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

Next Generation Nuclear Plant Materials Research and Development Program Plan  

SciTech Connect

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.

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

2005-09-01T23:59:59.000Z

342

Integrated safeguards & security for material protection, accounting, and control.  

SciTech Connect

Traditional safeguards and security design for fuel cycle facilities is done separately and after the facility design is near completion. This can result in higher costs due to retrofits and redundant use of data. Future facilities will incorporate safeguards and security early in the design process and integrate the systems to make better use of plant data and strengthen both systems. The purpose of this project was to evaluate the integration of materials control and accounting (MC&A) measurements with physical security design for a nuclear reprocessing plant. Locations throughout the plant where data overlap occurs or where MC&A data could be a benefit were identified. This mapping is presented along with the methodology for including the additional data in existing probabilistic assessments to evaluate safeguards and security systems designs.

Duran, Felicia Angelica; Cipiti, Benjamin B.

2009-10-01T23:59:59.000Z

343

Development of the RFID System for nuclear materials management.  

Science Conference Proceedings (OSTI)

Radio frequency identification (RFID) is one of today's most rapidly growing technologies in the automatic data collection industry. Although commercial applications are already widespread, the use of this technology for managing nuclear materials is only in its infancy. Employing an RFID system has the potential to offer an immense payback: enhanced safety and security, reduced need for manned surveillance, real-time access to status and event history data, and overall cost-effectiveness. The Packaging Certification Program (PCP) in the U.S. Department of Energy's (DOE's) Office of Environmental Management (EM), Office of Packaging and Transportation (EM-63), is developing an RFID system for nuclear materials management. The system consists of battery-powered RFID tags with onboard sensors and memories, a reader network, application software, a database server and web pages. The tags monitor and record critical parameters, including the status of seals, movement of objects, and environmental conditions of the nuclear material packages in real time. They also provide instant warnings or alarms when preset thresholds for the sensors are exceeded. The information collected by the readers is transmitted to a dedicated central database server that can be accessed by authorized users across the DOE complex via a secured network. The onboard memory of the tags allows the materials manifest and event history data to reside with the packages throughout their life cycles in storage, transportation, and disposal. Data security is currently based on Advanced Encryption Standard-256. The software provides easy-to-use graphical interfaces that allow access to all vital information once the security and privilege requirements are met. An innovative scheme has been developed for managing batteries in service for more than 10 years without needing to be changed. A miniature onboard dosimeter is being developed for applications that require radiation surveillance. A field demonstration of the RFID system was recently conducted to assess its performance. The preliminary results of the demonstration are reported in this paper.

Chen, K.; Tsai, H.; Liu, Y. Y. (Decision and Information Sciences)

2008-01-01T23:59:59.000Z

344

Nuclear membranes control symbiotic calcium signaling of legumes  

E-Print Network (OSTI)

Nuclear membranes control symbiotic calcium signaling of legumes Ward Capoena , Jongho Suna , Derin 13, 2011 (received for review May 18, 2011) Nuclear-associated oscillations in calcium act as a secondary messenger in the symbiotic signaling pathway of legumes. These are decoded by a nuclear

Sun, Jongho

345

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

DOE Patents (OSTI)

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.

Slaughter, Dennis R. (Oakland, CA); Pohl, Bertram A. (Berkeley, CA); Dougan, Arden D. (San Ramon, CA); Bernstein, Adam (Palo Alto, CA); Prussin, Stanley G. (Kensington, CA); Norman, Eric B. (Oakland, CA)

2008-04-15T23:59:59.000Z

346

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

Science Conference Proceedings (OSTI)

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.

Veirs, D Kirk [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

347

Guidance Tools for Use in Nuclear Material Management Decisions Making  

Science Conference Proceedings (OSTI)

This paper describes the results of Recommendation 14 of the Integrated Nuclear Materials Management Plan (INMMP) which was the product of a management initiative at the highest levels of the Department of Energy responding to a congressional directive to accelerate the work of achieving integration and cutting long-term costs associated with the management of nuclear materials, with the principal focus on excess materials. The INMMP provided direction to ''Develop policy-level decision support tools to support long-term planning and decision making.'' To accomplish this goal a team from the Savannah River Site, Sandia National Laboratories, Idaho National Engineering and Environmental Laboratory (INEEL), and the U.S. Department of Energy experienced in the decision-making process developed a Guidebook to Decision-Making Methods. The goal of the team organized to implement Recommendation 14 was to instill transparency, consistency, rigor, and discipline in the DOE decision process. The guidebook introduces a process and a selection of proven methods for disciplined decision-making so that the results are clearer, more transparent, and easier for reviewers to understand and accept. It was written to set a standard for a consistent decision process.

Johnson, G. V.; Baker, D. J.; Sorenson, K. B.; Boeke, S. G.

2002-02-26T23:59:59.000Z

348

TAMCN: a tool for aggregate modeling of civil nuclear materials  

E-Print Network (OSTI)

There has been some concern in recent years about the buildup of separated civil plutonium in the world. In order to address issues related to these concerns, it is useful to have models that provide quantitative predictions of this buildup, under various scenarios. Our goal was to develop a publicly available model that would allow users to specify scenarios of their own, not simply the scenarios we envisioned. We believe this approach will provide a more complete understanding of the processes involved in the creation, storage, and utilization of potentially destructive nuclear material. Western Europe and Japan, namely France, Belgium, the United Kingdom, Germany, Switzerland, and Japan, were chosen as a starting point because the issues present in these countries, we believe, represent the pressing issues in all nuclear countries and may fully address the current problems in the buildup of reactor grade plutonium in the world today. In addition, these countries have contributed a substantial quantity of material to the amount of civil separated plutonium present today, so we thought it wise to begin here. We have developed a model of the nuclear fuel cycle in Western Europe and Japan using STELLA. Our model uses the simple "stock and flow" structure of STELLA to describe the discharge, storage, and reprocessing of spent nuclear fuel from commercial power reactors, and the creation, storage, and utilization of reactor-grade civil separated plutonium in these regions. This provides an interface that is user-friendly and can be run on any computing platform that can operate the STELLA software. In addition, detailed changes can be easily made to the model, if the user desires. We will describe features of the model from the perspective of a user, give the results of a few scenarios, and delineate plausibility tests of the model.

Watson, Aaron Michael

2002-01-01T23:59:59.000Z

349

Materials for Nuclear Power: Digital Resource Center - WEB ... - TMS  

Science Conference Proceedings (OSTI)

Feb 16, 2007 ... Topic Title: WEB RESOURCE: Virtual Nuclear Tourist! Nuclear Plants Around the ... Nuclear Power Plants Around the World.22 January 2006.

350

Materials for Nuclear Power: Digital Resource Center - WEB ...  

Science Conference Proceedings (OSTI)

Topic Summary: A comprehensive glossary for nuclear chemistry, nuclear physics and nuclear engineering. Created On: 2/16/2007 2:04 PM, Topic View:.

351

Materials for Nuclear Power: Digital Resource Center - REPORT ...  

Science Conference Proceedings (OSTI)

Feb 12, 2007... Nuclear Power Background, Trends in Nuclear Power, The Nuclear ... Science: Application to Fusion and Generation IV Fission Reactors

352

BOOK: Environmental Degradation of Materials in Nuclear Power  

Science Conference Proceedings (OSTI)

Mar 28, 2007... Trends in Nuclear Power, The Nuclear Fuel Cycle, Nuclear Science ... associated with spent fuel storage and radioactive waste disposal.

353

Universal Control of Nuclear Spins Via Anisotropic Hyperfine Interactions  

E-Print Network (OSTI)

We show that nuclear spin subsystems can be completely controlled via microwave irradiation of resolved anisotropic hyperfine interactions with a nearby electron spin. Such indirect addressing of the nuclear spins via coupling to an electron allows us to create nuclear spin gates whose operational time is significantly faster than conventional direct addressing methods. We experimentally demonstrate the feasibility of this method on a solid-state ensemble system consisting of one electron and one nuclear spin.

Jonathan S. Hodges; Jamie C. Yang; Chandrasekhar Ramanathan; David G. Cory

2007-07-19T23:59:59.000Z

354

Nuclear Materials Management and Safeguards System Working Group Charter  

National Nuclear Security Administration (NNSA)

DRAFT 2011 DRAFT 2011 DRAFT 2011 Nuclear Materials Management and Safeguards System Working Group Charter VERSION: 0 REVISION DATE: May 2011 Approver Name Title Signature Date DRAFT 2011 DRAFT 2011 NMMSS Working Group Charter PURPOSE The NMMSS Working Group (NWG) serves as an open forum for discussion of issues and concerns from the NMMSS User community. The Committee will provide an interface between NMMSS users, NMMSS sponsors and the NMMSS project staff. Activities may include: Identifying user needs Identifying deficiencies in reporting capabilities Recommending upgrades to software capabilities Recommending priorities for modifications Recommending enhancements to data Minimizing the reporting burden on the reporting community

355

RADIOACTIVE MATERIALS LABORATORY SAFETY REPORT, MARTIN NUCLEAR FACILITY, QUEHANNA SITE  

SciTech Connect

A description is given of the safety features and the major alterations to be performed prior to occupancy. The evaluation was made in support of fubrication work on the production of safe isotopic power sources from Cm/sup 242/ and Sr/sup 90/. The chemical, nuclear, and radiobiological properties of Cm/sup 242/ and Sr/sup 90/ are outlined. The projected physical fiow of materials for production of the isotopic power souroes is schematically given. An evaluation of the malfunctions, operational hazards, and remedial health physics procedures is presented. The analysis and evaluation of postulated maximum credible incidents are demonstrated. (B.O.G.)

1960-09-01T23:59:59.000Z

356

Export control guide: Spent nuclear fuel reprocessing and preparation of plutonium metal  

Science Conference Proceedings (OSTI)

The international Treaty on the Non-Proliferation of Nuclear Weapons, also referred to as the Non-Proliferation Treaty (NPT), states in Article III, paragraph 2(b) that {open_quotes}Each State Party to the Treaty undertakes not to provide . . . equipment or material especially designed or prepared for the processing, use or production of special fissionable material to any non-nuclear-weapon State for peaceful purposes, unless the source or special fissionable material shall be subject to the safeguards required by this Article.{close_quotes} This guide was prepared to assist export control officials in the interpretation, understanding, and implementation of export laws and controls relating to the international Trigger List for irradiated nuclear fuel reprocessing equipment, components, and materials. The guide also contains information related to the production of plutonium metal. Reprocessing and its place in the nuclear fuel cycle are described briefly; the standard procedure to prepare metallic plutonium is discussed; steps used to prepare Trigger List controls are cited; descriptions of controlled items are given; and special materials of construction are noted. This is followed by a comprehensive description of especially designed or prepared equipment, materials, and components of reprocessing and plutonium metal processes and includes photographs and/or pictorial representations. The nomenclature of the Trigger List has been retained in the numbered sections of this document for clarity.

NONE

1993-10-01T23:59:59.000Z

357

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

National Nuclear Security Administration (NNSA)

Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

358

Accelerated Testing of Neutron-Absorbing Alloys for Nuclear Criticality Control  

Science Conference Proceedings (OSTI)

Special Issue Technical Paper / Second Seminar on Accelerated Testing of Materials in Spent Nuclear Fuel and High-Level Waste Storage Systems / Materials for Nuclear Systems

R. E. Mizia; T. E. Lister

359

R&D for Better Nuclear Security: Radiation Detector Materials  

SciTech Connect

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.

Kammeraad, J E

2009-04-02T23:59:59.000Z

360

R&D for Better Nuclear Security: Radiation Detector Materials  

SciTech Connect

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.

Kammeraad, J E

2009-04-02T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear material control" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

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

Science Conference Proceedings (OSTI)

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.

Jesse Schrieber

2008-07-01T23:59:59.000Z

362

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

SciTech Connect

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.

Jesse Schreiber

2008-03-01T23:59:59.000Z

363

Beyond integrated safeguards: performance-based assessments for future nuclear controls.  

Science Conference Proceedings (OSTI)

In the future, iE the nuclear nonproliferation and arms control agendas are to advance, they will likely become increasingly seen as parallel undertakings with the objective of comprehensive cradle-to-grave controls over nuclear materials and possibly even warheads removed from defense programs along with materials in civilian use. This 'back to the future' prospect was envisioned in the Acheson-Lillienthal Report and the Baruch Plan, and more modestly in the Atoms-for-Peace Proposal. Unlike the grand plans of the early nuclear years, today's and tomorrow's undertakings will more likely consist of a series of incremental steps with the goal of expanding nuclear controls. These steps will be undertaken at a time of fundamental change in the IAEA safeguards system, and they will be influenced by those changes in profound ways. This prospective influence needs to be taken into account as the IAEA develops and implements integrated safeguards, including its efforts to establish new safeguards criteria, undertake technological and administrative improvements in safeguards, implement credible capabilities for the detection of undeclared nuclear facilities and activities and, perhaps, provide for a more intensive involvement in applying safeguards in new roles such as the verification of a fissile materials cutoff treaty. Performance-based criteria offer one promising way to address the effectiveness of integrated safeguards and to provide a common means of assessing the other key areas of a comprehensive approach to nuclear controls as these develop independently and to the extent that they are coordinated in the future.

Pilat, Joseph F.; Budlong-Sylvester, K. W. (Kory W.)

2001-01-01T23:59:59.000Z

364

Nuclear Resonance Fluorescence for Material Verification in Dismantlement  

Science Conference Proceedings (OSTI)

Nuclear resonance fluorescence (NRF) is a well-established physical process that provides an isotope-specific signature that can be exploited for isotopic detection and characterization of samples. Pacific Northwest National Laboratory has been investigating possible applications of NRF for national security. Of the investigated applications, the verification of material in the dismantlement process is the most promising. Through a combination of benchmarking measurements and radiation transport modeling, we have shown that NRF techniques with existing bremsstrahlung photon sources and a modest detection system can be used to detect highly enriched uranium in the quantities and time limits relevant to the dismantlement process. Issues such as orientation, placement and material geometry do not significantly impact the sensitivity of the technique. We have also investigated how shielding of the uranium would be observed through non-NRF processes to enable the accurate assay of the material. This paper will discuss our findings on how NRF and photon-interrogation techniques may be applied to the material verification in the dismantlement process.

Warren, Glen A.; Detwiler, Rebecca S.

2011-10-01T23:59:59.000Z

365

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

Science Conference Proceedings (OSTI)

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.

NONE

1995-07-14T23:59:59.000Z

366

Conducting Well-Controlled Ion Irradiations To Understand Neutron Irradiation Effects In Materials  

Science Conference Proceedings (OSTI)

A firm understanding of the effect of radiation on materials is required to develop predictive models of materials behavior in-reactor and provide a foundation for creating new, more radiation-tolerant materials. Ion irradiation can serve this purpose for nuclear reactor components and is becoming a key element of materials development for advanced nuclear reactors. Ion irradiations can be conducted quickly, at low cost, and with precise control over irradiation temperature, temperature uniformity, dose rate, dose uniformity and total dose. During proton irradiations the 2{sigma}(twice the standard deviation) of the sample temperature is generally below {approx}7 deg. C, the dose rate variation {approx}3%, the dose uncertainty {approx}3%, and there is an excellent temperature and dose uniformity across the irradiated area. In this article, we describe the experimental setup and irradiation procedure used to conduct well-controlled ion irradiations at the University of Michigan.

Naab, F. U.; West, E. A.; Toader, O. F.; Was, G. S. [Department of Engineering and Radiological Sciences, College of Engineering, University of Michigan, 2355 Bonisteel Boulevard, Ann Arbor, MI 48109-2104 (United States)

2011-06-01T23:59:59.000Z

367

Impact of nuclear fuel cycle centers on shipping special nuclear materials and wastes  

SciTech Connect

The impact of integrated nuclear fuel cycle facilities on the transportation sector appears from this admittedly rather narrow study to be of only marginal significance. However, there are other factors which must be taken into account such as nuclear safeguards, economics, and radiological, ecological, institutional, and sociological impacts. Unless more clear-cut advantages can be shown by on-going studies for some of these other considerations, the regimentation and control of industry that would result from the imposition of the integrated fuel cycle facility concept probably could not be justified. (auth)

Blomeke, J.O.

1975-01-01T23:59:59.000Z

368

Nevada Nuclear Waste Storage Investigations: Exploratory Shaft Facility fluids and materials evaluation  

Science Conference Proceedings (OSTI)

The objective of this study was to determine if any fluids or materials used in the Exploratory Shaft Facility (ESF) of Yucca Mountain will make the mountain unsuitable for future construction of a nuclear waste repository. Yucca Mountain, an area on and adjacent to the Nevada Test Site in southern Nevada, USA, is a candidate site for permanent disposal of high-level radioactive waste from commercial nuclear power and defense nuclear activities. To properly characterize Yucca Mountain, it will be necessary to construct an underground test facility, in which in situ site characterization tests can be conducted. The candidate repository horizon at Yucca Mountain, however, could potentially be compromised by fluids and materials used in the site characterization tests. To minimize this possibility, Los Alamos National Laboratory was directed to evaluate the kinds of fluids and materials that will be used and their potential impacts on the site. A secondary objective was to identify fluids and materials, if any, that should be prohibited from, or controlled in, the underground. 56 refs., 19 figs., 11 tabs.

West, K.A.

1988-11-01T23:59:59.000Z

369

Environmental assessment for consolidation of certain materials and machines for nuclear criticality experiments and training  

Science Conference Proceedings (OSTI)

In support of its assigned missions and because of the importance of avoiding nuclear criticality accidents, DOE has adopted a policy to reduce identifiable nuclear criticality safety risks and to protect the public, workers, government property and essential operations from the effects of a criticality accident. In support of this policy, the Los Alamos Critical Experiments Facility (LACEF) at the Los Alamos National Laboratory (LANL) Technical Area (TA) 18, provides a program of general purpose critical experiments. This program, the only remaining one of its kind in the United States, seeks to maintain a sound basis of information for criticality control in those physical situations that DOE will encounter in handling and storing fissionable material in the future, and ensuring the presence of a community of individuals competent in practicing this control.

NONE

1996-05-21T23:59:59.000Z

370

Criticality control in shipments of fissile materials  

SciTech Connect

This paper describes a procedure for finite-array criticality analysis to ensure criticality safety of shipments of fissile materials in US DOE-certified packages. After the procedure has been performed, one can obtain the minimum transport index and determine the maximum number of fissile packages allowable in a shipment that meets the 10 CFR 71 criticality safety requirements.

Liaw, J. R.; Liu, Y. Y.

2000-03-14T23:59:59.000Z

371

S&TR | January/February 2007: Identifying the Source of Nuclear Materials  

NLE Websites -- All DOE Office Websites (Extended Search)

January/February 2007 January/February 2007 The Laboratory in the News Commentary by George H. Miller Titan Leads the Way in Laser-Matter Science Identifying the Source of Stolen Nuclear Materials Tiny Tubes Make the Flow Go Acidic Microbe Community Fosters the Unique Patents and Awards S&TR Staff Article title: Identifying the Source of Stolen Nuclear Materials; article blurb: Livermore scientists are analyzing interdicted illicit nuclear and radioactive materials for clues to the materials' origins and routes of transit. NUCLEAR forensics and attribution are becoming increasingly important tools in the fight against illegal smuggling and trafficking of radiological and nuclear materials. These include materials intended for industrial and medical use (radiological), nuclear materials such as those produced in the

372

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

Office of Science (SC) Website

Nuclear Science Advisory Committee (NSAC) News & Resources Contact Information Nuclear Physics U.S. Department of Energy SC-26Germantown Building 1000 Independence...

373

Materials for Nuclear Power: Digital Resource Center - WEB ...  

Science Conference Proceedings (OSTI)

Mar 8, 2007 ... The Nuclear Engineering Department Heads Organization (NEDHO) is a loosely formed alliance of Heads (Chairs) of Nuclear Engineering...

374

Materials for Nuclear Power: Digital Resource Center - WEB ...  

Science Conference Proceedings (OSTI)

May 15, 2007 ... Sponsored by the U.S. Nuclear Regulatory Commission, the Center for Nuclear Waste Regulatory Analyses has as its overall mission to...

375

Materials for Nuclear Power: Digital Resource Center - WEB ...  

Science Conference Proceedings (OSTI)

Feb 16, 2007 ... Topic Title: WEB RESOURCE: Nuclear Energy Institute Topic Summary: Timely coverage of developments in the the nuclear power industry

376

Materials for Nuclear Power: Digital Resource Center -- Articles and ...  

Science Conference Proceedings (OSTI)

BOOK: Safety Related Issues of Spent Nuclear Fuel Storage ... ARTICLES: High- Radiation Nuclear Waste Disposal ... S. Zhu, et. al., Applied Physics Letters.

377

Materials for the Nuclear Renaissance II - Programmaster.org  

Science Conference Proceedings (OSTI)

Aug 2, 2010 ... Nuclear energy does not release carbon dioxide to the atmosphere and ... for used nuclear fuel, and (5) decommissioning, decontamination.

378

Materials for Nuclear Power: Digital Resource Center Text Topic  

Science Conference Proceedings (OSTI)

Feb 19, 2007 ... Emphasis is placed on their contributions to nuclear science and technology, within the context of ... Department of Nuclear Engineering.

379

Special Topics: Nuclear Materials: On-line tutorials  

Science Conference Proceedings (OSTI)

Jun 28, 2007 ... TUTORIALS: Nuclear Chemistry and the Origins of the Elements Chemistry - The ... Nuclear Science Division, Lawrence Berkeley National Lab.

380

Materials for Nuclear Power: Digital Resource Center - REPORT ...  

Science Conference Proceedings (OSTI)

Feb 12, 2007 ... A resource document for the Workshop on Basic Research Needs for Advanced Nuclear Energy Systems. Includes an overview of nuclear...

Note: This page contains sample records for the topic "nuclear material control" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

Materials for Nuclear Power: Digital Resource Center - WEB ...  

Science Conference Proceedings (OSTI)

Feb 16, 2007 ... This page provides a review of nuclear chemistry, including notes and case studies, for two 45-minute classes. Topics range from basic nuclear...

382

Materials for Nuclear Power: Digital Resource Center - VIDEO ...  

Science Conference Proceedings (OSTI)

Jun 13, 2007 ... Topic Title: VIDEO: Global Nuclear Energy Partnership (GNEP): A vision for nuclear-enabled peace and prosperity in the 21st century

383

Materials for Nuclear Power: Digital Resource Center - WEB ...  

Science Conference Proceedings (OSTI)

Oct 24, 2007 ... Nuclear Regulatory Commission Information Digest contains up-to-date information about the agency, domestic and worldwide nuclear energy,...

384

Materials for Nuclear Power: Digital Resource Center Text Topic - TMS  

Science Conference Proceedings (OSTI)

Feb 16, 2007 ... Office of Nuclear Energy and Office of Advanced Scientific Computing Research. Simulation and Modeling for Advanced Nuclear Energy...

385

Materials for Nuclear Power: Digital Resource Center - PDF ...  

Science Conference Proceedings (OSTI)

Feb 16, 2007 ... Office of Nuclear Energy and Office of Advanced Scientific Computing Research. Simulation and Modeling for Advanced Nuclear Energy...

386

Materials for Nuclear Power: Digital Resource Center - PDF ...  

Science Conference Proceedings (OSTI)

Feb 12, 2007 ... SOURCE: United States. Department of Energy, Office of Nuclear Energy, Science and Technology. Answers to Questions: Nuclear Energy,...

387

Ultra Wide Band RFID Neutron Tags for Nuclear Materials Monitoring  

SciTech Connect

Recent advancements in the ultra-wide band Radio Frequency Identification (RFID) technology and solid state pillar type neutron detectors have enabled us to move forward in combining both technologies for advanced neutron monitoring. The LLNL RFID tag is totally passive and will operate indefinitely without the need for batteries. The tag is compact, can be directly mounted on metal, and has high performance in dense and cluttered environments. The LLNL coin-sized pillar solid state neutron detector has achieved a thermal neutron detection efficiency of 20% and neutron/gamma discrimination of 1E5. These performance values are comparable to a fieldable {sup 3}He based detector. In this paper we will discuss features about the two technologies and some potential applications for the advanced safeguarding of nuclear materials.

Nekoogar, F; Dowla, F; Wang, T

2010-01-27T23:59:59.000Z

388

Global threat reduction initiative Russian nuclear material removal progress  

SciTech Connect

In December 1999 representatives from the United States, the Russian Federation, and the International Atomic Energy Agency (IAEA) started discussing a program to return to Russia Soviet- or Russian-supplied highly enriched uranium (HEU) fuel stored at the Russian-designed research reactors outside Russia. Trilateral discussions among the United States, Russian Federation, and the International Atomic Energy Agency (IAEA) have identified more than 20 research reactors in 17 countries that have Soviet- or Russian-supplied HEU fuel. The Global Threat Reduction Initiative's Russian Research Reactor Fuel Return Program is an important aspect of the U.S. Government's commitment to cooperate with the other nations to prevent the proliferation of nuclear weapons and weapons-usable proliferation-attractive nuclear materials. To date, 496 kilograms of Russian-origin HEU have been shipped to Russia from Serbia, Latvia, Libya, Uzbekistan, Romania, Bulgaria, Poland, Germany, and the Czech Republic. The pilot spent fuel shipment from Uzbekistan to Russia was completed in April 2006. (author)

Cummins, Kelly [DOE/NNSA (United States); Bolshinsky, Igor [INL/NNSA (United States)

2008-07-15T23:59:59.000Z

389

Securing special nuclear material: Recent advances in neutron detection and their role in nonproliferation  

Science Conference Proceedings (OSTI)

Neutrondetection is an integral part of the global effort to prevent the proliferation of special nuclear material (SNM). Applications relying on neutron-detection technology range from traditional nuclear nonproliferation objectives

R. C. Runkle; A. Bernstein; P. E. Vanier

2010-01-01T23:59:59.000Z

390

Safety Board Recommendation 94-1, Remediation ofNuclear Materials in the  

E-Print Network (OSTI)

1998. Revision 2 describes the current status ofand changes to the Department's plans for stabilizing the nuclear materials. We plan to further revise this document over the next several months to reflect new plans at several sites, and the recently-issued Recommendation 2000-1, which also addresses our nuclear materials stabilization activities. The enclosed revision updates commitments for materials stabilization at the

The Honorable; John T. Conway

2000-01-01T23:59:59.000Z

391

Material protection, control and accounting cooperation at the Urals Electrochemical Integrated Plant (UEIP), Novouralsk, Russia  

Science Conference Proceedings (OSTI)

The Urals Electrochemical Integrated Plant is one of the Russian Ministry of Atomic Energy`s nuclear material production sites participating in the US Department of Energy`s Material Protection, Control and Accounting (MPC&A) Program. The Urals Electrochemical Integrated Plant is Russia`s largest uranium enrichment facility and blends tons of high-enriched uranium into low enriched uranium each year as part of the US high-enriched uranium purchase. The Electrochemical Integrated Plant and six participating national laboratories are cooperating to implement a series of enhancements to the nuclear material protection, control, and accountability systems at the site This paper outlines the overall objectives of the MPC&A program at Urals Electrochemical Integrated Plant and the work completed as of the date of the presentation.

McAllister, S., LLNL

1998-07-15T23:59:59.000Z

392

Flammability Control In A Nuclear Waste Vitrification System  

SciTech Connect

The Defense Waste Processing Facility at the Savannah River Site processes high-level radioactive waste from the processing of nuclear materials that contains dissolved and precipitated metals and radionuclides. Vitrification of this waste into borosilicate glass for ultimate disposal at a geologic repository involves chemically modifying the waste to make it compatible with the glass melter system. Pretreatment steps include removal of excess aluminum by dissolution and washing, and processing with formic and nitric acids to: 1) adjust the reduction-oxidation (redox) potential in the glass melter to reduce radionuclide volatility and improve melt rate; 2) adjust feed rheology; and 3) reduce by steam stripping the amount of mercury that must be processed in the melter. Elimination of formic acid in pretreatment has been studied to eliminate the production of hydrogen in the pretreatment systems, which requires nuclear grade monitoring equipment. An alternative reductant, glycolic acid, has been studied as a substitute for formic acid. However, in the melter, the potential for greater formation of flammable gases exists with glycolic acid. Melter flammability is difficult to control because flammable mixtures can be formed during surges in offgases that both increase the amount of flammable species and decrease the temperature in the vapor space of the melter. A flammable surge can exceed the 60% of the LFL with no way to mitigate it. Therefore, careful control of the melter feed composition based on scaled melter surge testing is required. The results of engineering scale melter tests with the formic-nitric flowsheet and the use of these data in the melter flammability model are presented.

Zamecnik, John R.; Choi, Alexander S.; Johnson, Fabienne C.; Miller, Donald H.; Lambert, Daniel P.; Stone, Michael E.; Daniel, William E. Jr.

2013-07-25T23:59:59.000Z

393

Materials and Fuels for the Current and Advanced Nuclear Reactors II  

Science Conference Proceedings (OSTI)

Lifetime extension of reactors - nuclear materials aging, degradation and others ... A Rate-Theory Approach to Irradiation Damage Modeling with Random...

394

Materials and Fuels for the Current and Advanced Nuclear Reactors III  

Science Conference Proceedings (OSTI)

Jul 15, 2013 ... Lifetime extension of reactors - nuclear materials aging, degradation and ... A Theoretical Model of Corrosion Rate Distribution in Liquid LBE...

395

Controlled low strength materials (CLSM), reported by ACI Committee 229  

Science Conference Proceedings (OSTI)

Controlled low-strength material (CLSM) is a self-compacted, cementitious material used primarily as a backfill in lieu of compacted fill. Many terms are currently used to describe this material including flowable fill, unshrinkable fill, controlled density fill, flowable mortar, flowable fly ash, fly ash slurry, plastic soil-cement, soil-cement slurry, K-Krete and other various names. This report contains information on applications, material properties, mix proportioning, construction and quality-control procedures. This report`s intent is to provide basic information on CLSM technology, with emphasis on CLSM material characteristics and advantages over conventional compacted fill. Applications include backfills, structural fills, insulating and isolation fills, pavement bases, conduit bedding, erosion control, void filling, and radioactive waste management.

Rajendran, N.

1997-07-01T23:59:59.000Z

396

97 percent of special nuclear material de-inventoried from LLNL | National  

National Nuclear Security Administration (NNSA)

97 percent of special nuclear material de-inventoried from LLNL | National 97 percent of special nuclear material de-inventoried from LLNL | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > NNSA Blog > 97 percent of special nuclear material de-inventoried ... 97 percent of special nuclear material de-inventoried from LLNL Posted By Office of Public Affairs

397

Nuclear reactor remote disconnect control rod coupling indicator  

DOE Patents (OSTI)

A coupling indicator for use with nuclear reactor control rod assemblies which have remotely disengageable couplings between the control rod and the control rod drive shaft. The coupling indicator indicates whether the control rod and the control rod drive shaft are engaged or disengaged. A resistive network, utilizing magnetic reed switches, senses the position of the control rod drive mechanism lead screw and the control rod position indicating tube, and the relative position of these two elements with respect to each other is compared to determine whether the coupling is engaged or disengaged.

Vuckovich, Michael (McKeesport, PA)

1977-01-01T23:59:59.000Z

398

Materials for Nuclear Power: Digital Resource Center - WEB ...  

Science Conference Proceedings (OSTI)

Feb 12, 2007 ... The "Inside a Nuclear Power Plant" section of this web page gives a brief and very basic introduction to the major systems in a nuclear power...

399

Materials for Nuclear Power: Digital Resource Center - WEB ...  

Science Conference Proceedings (OSTI)

Jun 13, 2007 ... Presentations from the ACTINET Thermodynamics of Nuclear Fuels: ... Fuels and Transmutation Targets and Fission Product Chemistry.

400

Materials for Nuclear Power: Digital Resource Center - WEB ...  

Science Conference Proceedings (OSTI)

Jun 13, 2007 ... Presentations from the ACTINET Thermodynamics of Nuclear Fuels: workshop. Topics include Theoretical Thermodynamics, Experimental...

Note: This page contains sample records for the topic "nuclear material control" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

Materials for Nuclear Power: Digital Resource Center - BOOK ...  

Science Conference Proceedings (OSTI)

Feb 12, 2007 ... It has been written primarily for advanced undergraduate and beginning graduate students in Nuclear Engineering, Radiation Physics,...

402

Materials for Nuclear Power: Digital Resource Center - WEB ...  

Science Conference Proceedings (OSTI)

Feb 19, 2007 ... FORUMS > NUCLEAR ENGINEERING ORGANIZATIONS ... Topic Summary: Overviews of the research sections in the Energy Technology...

403

Environmental Degradation of Materials in Nuclear Power Systems ...  

Science Conference Proceedings (OSTI)

... GE Nuclear Energy; Natraj Iyer, Westinghouse; Christer Jansson, VATTENFALL; Phil Lichtenberger, Ontario Hydro Technologies; Gene Lucas, University of...

404

Material-controlled dynamic vacuum insulation  

DOE Patents (OSTI)

A compact vacuum insulation panel is described comprising a chamber enclosed by two sheets of metal, glass-like spaces disposed in the chamber between the sidewalls, and a high-grade vacuum in the chamber includes apparatus and methods for enabling and disabling, or turning ``on`` and ``off`` the thermal insulating capability of the panel. One type of enabling and disabling apparatus and method includes a metal hydride for releasing hydrogen gas into the chamber in response to heat, and a hydrogen grate between the metal hydride and the chamber for selectively preventing and allowing return of the hydrogen gas to the metal hydride. Another type of enabling and disabling apparatus and method includes a variable emissivity coating on the sheets of metal in which the emissivity is controllably variable by heat or electricity. Still another type of enabling and disabling apparatus and method includes metal-to-metal contact devices that can be actuated to establish or break metal-to-metal heat paths or thermal short circuits between the metal sidewalls. 25 figs.

Benson, D.K.; Potter, T.F.

1996-10-08T23:59:59.000Z

405

Material-controlled dynamic vacuum insulation  

DOE Green Energy (OSTI)

A compact vacuum insulation panel comprising a chamber enclosed by two sheets of metal, glass-like spaces disposed in the chamber between the sidewalls, and a high-grade vacuum in the chamber includes apparatus and methods for enabling and disabling, or turning "on" and "off" the thermal insulating capability of the panel. One type of enabling and disabling apparatus and method includes a metal hydride for releasing hydrogen gas into the chamber in response to heat, and a hydrogen grate between the metal hydride and the chamber for selectively preventing and allowing return of the hydrogen gas to the metal hydride. Another type of enabling and disabling apparatus and method includes a variable emissivity coating on the sheets of metal in which the emissivity is controllably variable by heat or electricity. Still another type of enabling and disabling apparatus and method includes metal-to-metal contact devices that can be actuated to establish or break metal-to-metal heat paths or thermal short circuits between the metal sidewalls.

Benson, David K. (14154 W. First Dr., Golden, CO 80401); Potter, Thomas F. (515 S. Magnolia La., Denver, CO 80224)

1996-10-08T23:59:59.000Z

406

Advancements in Nuclear Materials Research at the Idaho National ...  

Science Conference Proceedings (OSTI)

... Atom Probe (LEAP) and Transmission Electron Microscope (TEM) capable of ... Limited Materials Availability: Considering the Importance of Materials Market...

407

Nuclear fusion control-oriented plasma physics  

Science Conference Proceedings (OSTI)

The development of control techniques for the efficient and reliable operation of a fusion reactor is one of the most challenging issues nowadays and it would provide great advantages over existing energy sources: Unlimited fuel availability, no greenhouse ... Keywords: fusion control, plasma physics, tokamak modeling and simulation

Aitor J. Garrido; Izaskun Garrido; M. Goretti Sevillano-Berasategui; Mikel Alberdi; Modesto Amundarain; Oscar Barambones; Itziar Martija

2009-07-01T23:59:59.000Z

408

CONTROL MEANS FOR A NUCLEAR REACTOR  

DOE Patents (OSTI)

A control means is described for a reactor which employs a liquid fuel consisting of a fissile isotope in a liquid bismuth solvent. The liquid fuel is contained in a plurality of tubular vessels. Control is effected by inserting plungers in the vessels to displace the liquid fuel and provide a critical or non- critical fuel configuration as desired.

Teitel, R.J.

1961-09-01T23:59:59.000Z

409

Process of making porous ceramic materials with controlled porosity  

DOE Patents (OSTI)

A method of making metal oxide ceramic material is disclosed by which the porosity of the resulting material can be selectively controlled by manipulating the sol used to make the material. The method can be used to make a variety of metal oxide ceramic bodies, including membranes, but also pellets, plugs or other bodies. It has also been found that viscous sol materials can readily be shaped by extrusion into shapes typical of catalytic or adsorbent bodies used in industry, to facilitate the application of such materials for catalytic and adsorbent applications.

Anderson, Marc A. (Madison, WI); Ku, Qunyin (Madison, WI)

1993-01-01T23:59:59.000Z

410

Passive neutron techniques for the nondestructive assay of nuclear material  

E-Print Network (OSTI)

Three drums containing potentially contaminated lead bricks were assayed with the Segmented Gamma Scan Neutron Assay System (SGSNAS) at Pacific Northwest National Laboratory's (PNNL) Nondestructive Assay Center. The assay system reported that the drums contained transuranic material. These results were based solely on the number of time-correlated neutron events. The gamma spectra for all three drums were inspected and no gamma ray lines corresponding to transuranic nuclides were found. Further investigations found that the lead in one of the drums had not been part of a contaminated area cleanup and should not be radiologically contaminated. This thesis examines the nuclear reactions that produce neutrons, the principles of neutron detectors including the circuitry required for coincidence counting, and how neutrons interact with matter. The premise is that time-correlated neutrons are produced from high-energy muon interactions with the lead nucleus, a spallation reaction. Muons are a component of the "air shower cascade" as cosmic rays traverse through the earth's atmosphere; therefore, an extensive study of cosmic rays has been undertaken. Verification that time-correlated neutrons are emitted from lead was performed using three completely separate systems.

Mapili, Gabriel

2000-01-01T23:59:59.000Z

411

Nuclear reactivity control using laser induced polarization  

DOE Patents (OSTI)

A control element for reactivity control of a fission source provides an atomic density of .sup.3 He in a control volume which is effective to control criticality as the .sup.3 He is spin-polarized. Spin-polarization of the .sup.3 He affects the cross section of the control volume for fission neutrons and hence, the reactivity. An irradiation source is directed within the .sup.3 He for spin-polarizing the .sup.3 He. An alkali-metal vapor may be included with the .sup.3 He where a laser spin-polarizes the alkali-metal atoms which in turn, spin-couple with .sup.3 He to spin-polarize the .sup.3 He atoms.

Bowman, Charles D. (Los Alamos, NM)

1991-01-01T23:59:59.000Z

412

Nuclear reactivity control using laser induced polarization  

DOE Patents (OSTI)

A control element for reactivity control of a fission source provides an atomic density of .sup.3 He in a control volume which is effective to control criticality as the .sup.3 He is spin-polarized. Spin-polarization of the .sup.3 He affects the cross section of the control volume for fission neturons and hence, the reactivity. An irradiation source is directed within the .sup.3 He for spin-polarizing the .sup.3 He. An alkali-metal vapor may be included with the .sup.3 He where a laser spin-polarizes the alkali-metal atoms which in turn, spin-couple with .sup.3 He to spin-polarize the .sup.3 He atoms.

Bowman, Charles D. (Los Alamos, NM)

1990-01-01T23:59:59.000Z

413

Nuclear reactivity control using laser induced polarization  

DOE Patents (OSTI)

A control element for reactivity control of a fission source provides an atomic density of {sup 3}He in a control volume which is effective to control criticality as the {sup 3}He is spin-polarized. Spin-polarization of the {sup 3}He affects the cross section of the control volume for fission neutrons and hence, the reactivity. An irradiation source is directed within the {sup 3}He for spin-polarizing the {sup 3}He. An alkali-metal vapor may be included with the {sup 3}He where a laser spin-polarizes the alkali-metal atoms which in turn, spin-couple with {sup 3}He to spin-polarize the {sup 3}He atoms. 5 figs.

Bowman, C.D.

1989-05-26T23:59:59.000Z

414

Nuclear safety surveillance and control of National Nuclear Safety Administration of PRC during commissioning and operation of nuclear power plants  

Science Conference Proceedings (OSTI)

This article describes the method of nuclear safety surveillance and control of National Nuclear Safety Administration (NNSA) of PRC during commissioning and operation of nuclear power plants (NPPs) and the practice for Qinshan NPP and for Guangdong Daya Bay NPP (GNPS). The results of the practice show that the surveillance models set up for Qinshan NPP and for GNPS commissioning were effective and the surveillance has played an important role for ensuring the quality and safety of the commissioning testing and consequently the nuclear safety of these two plants.

Feng, W.; Zhang, C.

1994-12-31T23:59:59.000Z

415

Special nuclear materials cutoff exercise: Issues and lessons learned. Volume 1: Summary of exercise  

Science Conference Proceedings (OSTI)

In a September 1993 address to the United Nations General Assembly, President Clinton announced a new nonproliferation and export control policy that established a framework for US efforts to prevent the proliferation of weapons of mass destruction. The new policy proposed that the US undertake a comprehensive approach to the growing accumulation of fissile material. One of the key elements was for the US to support a special nuclear materials (SNM) multilateral convention prohibiting the production of highly enriched uranium (HEU) or plutonium for nuclear explosives purposes or outside of international safeguards. This policy is often referred to as the President`s Cutoff Initiative or the Fissile Material Cutoff Treaty (FMCT). Because both the US Department of Energy (DOE) and foreign reprocessing facilities similar to PUREX will likely to be inspected under a FMCT, the DOE Office of Arms Control and Nonproliferation, Negotiations and Analysis Division (DOE/NN-41) tasked Pacific Northwest Laboratory (PNL) to perform an information gathering exercise, the PUREX Exercise, using the Plutonium-Uranium Extraction (PUREX) Plant located on the Hanford Site in Washington State. PUREX is a former production reactor fuel reprocessing plant currently undergoing a transition to a ``decontamination and decommissioning (D&D) ready`` mode. The PUREX Exercise was conducted March 29--30, 1994, to examine aspects of the imposition of several possible cutoff regimes and to study verification of non-production of SNM for nuclear weapons purposes or outside of safeguards. A follow-up activity to further examine various additional verification regimes was held at Los Alamos National Laboratory (LANL) on May 10, 1994.

Libby, R.A.; Davis, C. [Pacific Northwest Lab., Richland, WA (United States); Segal, J.E.; Stanbro, W.D. [Los Alamos National Lab., NM (United States)

1995-08-01T23:59:59.000Z

416

ANNOUNCEMENT NUCLEAR ENGINEERING FACULTY POSITION  

E-Print Network (OSTI)

safeguards, radiation interaction with materials including human tissue, nuclear fuels performance at the University of Tennessee, Knoxville (UTK) is seeking qualified individuals for a Tenure Track faculty position instrumentation & controls, monitoring and diagnostics, reactor dynamics, nuclear security, nuclear materials

Tennessee, University of

417

Nuclear reactor and materials science research: Technical report, May 1, 1985-September 30, 1986  

Science Conference Proceedings (OSTI)

Throughout the 17-month period of its grant, May 1, 1985-September 30, 1986, the MIT Research Reactor (MITR-II) was operated in support of research and academic programs in the physical and life sciences and in related engineering fields. The reactor was operated 4115 hours during FY 1986 and for 6080 hours during the entire 17-month period, an average of 82 hours per week. Utilization of the reactor during that period may be classified as follows: neutron beam tube research; nuclear materials research and development; radiochemistry and trace analysis; nuclear medicine; radiation health physics; computer control of reactors; dose reduction in nuclear power reactors; reactor irradiations and services for groups outside MIT; MIT Research Reactor. Data on the above utilization for FY 1986 show that the MIT Nuclear Reactor Laboratory (NRL) engaged in joint activities with nine academic departments and interdepartmental laboratories at MIT, the Charles Stark Draper Laboratory in Cambridge, and 22 other universities and nonprofit research institutions, such as teaching hospitals.

Not Available

1987-05-11T23:59:59.000Z

418

CONTROL ROD FOR A NUCLEAR REACTOR AND METHOD OF PREPARATION  

DOE Patents (OSTI)

BS>An improved control rod is presented for a nuclear reactor. This control rod is comprised of a rare earth metal oxide or rare earth metal carbide such as gadolinium oxide or gadolinium carbide, uniformly distributed in a metal matrix having a low cross sectional area of absorption for thermal neutrons, such as aluminum, beryllium, and zirconium.

Hausner, H.H.

1958-12-30T23:59:59.000Z

419

Algorithms for raw material dosage control for cement plants  

Science Conference Proceedings (OSTI)

The raw material used for producing cement is obtained using several components which we must dosages so that the mixture should have a uniform chemical composition. This paper work proposes fuzzy algorithms for performing this process. Using them turns ... Keywords: algorithm, cement, control, dosage, fuzzy, raw material

Stela Rusu-Anghel; Ovidiu Tirian; Osaci Mihaela; Dinis Corina

2009-07-01T23:59:59.000Z

420

Summary of "Materials Modeling and Simulations for Nuclear Fuels"  

NLE Websites -- All DOE Office Websites (Extended Search)

Summary of "Materials Modeling and Simulations for Nuclear Fuels" Summary of "Materials Modeling and Simulations for Nuclear Fuels" (MMSNF 2013) workshop Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library About Nuclear Energy Nuclear Reactors Designed by Argonne Argonne's Nuclear Science and Technology Legacy Opportunities within NE Division Visit Argonne Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Celebrating the 70th Anniversary of Chicago Pile 1 (CP-1) Argonne OutLoud on Nuclear Energy Argonne Energy Showcase 2012 Highlights Bookmark and Share "Materials Modeling and Simulations for Nuclear Fuels" (MMSNF 2013) workshop Workshop Summary Presentation during MMSNF Workshop in Chicago

Note: This page contains sample records for the topic "nuclear material control" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

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 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 1, 2013 Revision History Date Revision Description October 2008 1.0 Initial release April 2013 2.0 New release NMMSS User Guide 2.0 i April 1, 2013 Table of Contents Section 1 Introduction ...................................................................................................................... 1-1

422

Implementation of an Enhanced Measurement Control Program for handling nuclear safety samples at WSRC  

SciTech Connect

In the separation and purification of nuclear material, nuclear criticality safety (NCS) is of primary concern. The primary nuclear criticality safety controls utilized by the Savannah River Site (SRS) Separations Facilities involve administrative and process equipment controls. Additional assurance of NCS is obtained by identifying key process hold points where sampling is used to independently verify the effectiveness of production control. Nuclear safety measurements of samples from these key process locations provide a high degree of assurance that processing conditions are within administrative and procedural nuclear safety controls. An enhanced procedure management system aimed at making improvements in the quality, safety, and conduct of operation was implemented for Nuclear Safety Sample (NSS) receipt, analysis, and reporting. All procedures with nuclear safety implications were reviewed for accuracy and adequate detail to perform the analytical measurements safely, efficiently, and with the utmost quality. Laboratory personnel worked in a ``Deliberate Operating`` mode (a systematic process requiring continuous expert oversight during all phases of training, testing, and implementation) to initiate the upgrades. Thus, the effort to revise and review nuclear safety sample procedures involved a team comprised of a supervisor, chemist, and two technicians for each procedure. Each NSS procedure was upgraded to a ``Use Every Time`` (UET) procedure with sign-off steps to ensure compliance with each step for every nuclear safety sample analyzed. The upgrade program met and exceeded both the long and short term customer needs by improving measurement reliability, providing objective evidence of rigid adherence to program principles and requirements, and enhancing the system for independent verification of representative sampling from designated NCS points.

Boler-Melton, C.; Holland, M.K.

1991-12-31T23:59:59.000Z

423

Implementation of an Enhanced Measurement Control Program for handling nuclear safety samples at WSRC  

SciTech Connect

In the separation and purification of nuclear material, nuclear criticality safety (NCS) is of primary concern. The primary nuclear criticality safety controls utilized by the Savannah River Site (SRS) Separations Facilities involve administrative and process equipment controls. Additional assurance of NCS is obtained by identifying key process hold points where sampling is used to independently verify the effectiveness of production control. Nuclear safety measurements of samples from these key process locations provide a high degree of assurance that processing conditions are within administrative and procedural nuclear safety controls. An enhanced procedure management system aimed at making improvements in the quality, safety, and conduct of operation was implemented for Nuclear Safety Sample (NSS) receipt, analysis, and reporting. All procedures with nuclear safety implications were reviewed for accuracy and adequate detail to perform the analytical measurements safely, efficiently, and with the utmost quality. Laboratory personnel worked in a Deliberate Operating'' mode (a systematic process requiring continuous expert oversight during all phases of training, testing, and implementation) to initiate the upgrades. Thus, the effort to revise and review nuclear safety sample procedures involved a team comprised of a supervisor, chemist, and two technicians for each procedure. Each NSS procedure was upgraded to a Use Every Time'' (UET) procedure with sign-off steps to ensure compliance with each step for every nuclear safety sample analyzed. The upgrade program met and exceeded both the long and short term customer needs by improving measurement reliability, providing objective evidence of rigid adherence to program principles and requirements, and enhancing the system for independent verification of representative sampling from designated NCS points.

Boler-Melton, C.; Holland, M.K.

1991-01-01T23:59:59.000Z

424

Nuclear reactor flow control method and apparatus  

DOE Patents (OSTI)

Method and apparatus for improving coolant flow in a nuclear reactor during accident as well as nominal conditions. The reactor has a plurality of fuel elements in sleeves and a plenum above the fuel and through which the sleeves penetrate. Holes are provided in the sleeve so that coolant from the plenum can enter the sleeve and cool the fuel. The number and size of the holes are varied from sleeve to sleeve with the number and size of holes being greater for sleeves toward the center of the core and less for sleeves toward the periphery of the core. Preferably the holes are all the same diameter and arranged in rows and columns, the rows starting from the bottom of every sleeve and fewer rows in peripheral sleeves and more rows in the central sleeves.

Church, J.P.

1993-03-30T23:59:59.000Z

425

Nuclear reactor flow control method and apparatus  

DOE Patents (OSTI)

This document describes method and apparatus for improving coolant flow in a nuclear reactor during accident as well as nominal conditions. The reactor has a plurality of fuel elements in sleeves and a plenum above the fuel and through which the sleeves penetrate. Holes are provided in the sleeve so that coolant from the plenum can enter the sleeve and cool the fuel. The number and size of the holes are varied from sleeve to sleeve with the number and size of holes being greater for sleeves toward the center of the core and less for sleeves toward the periphery of the core. Preferably the holes are all the same diameter and arranged in rows and columns, the rows starting from the bottom of every sleeve and fewer rows in peripheral sleeves and more rows in the central sleeves.

Church, J.P.

1991-04-23T23:59:59.000Z

426

NNSAs Management of the $245 million Nuclear Materials Safeguards and Security Upgrades Project Phase II at Los Alamos National Laboratory  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

NNSA's Management of the $245 NNSA's Management of the $245 Million Nuclear Materials Safeguards and Security Upgrades Project Phase II DOE/IG-0901 January 2014 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections Department of Energy Washington, DC 20585 January 2, 2014 MEMORANDUM FOR THE SECRETARY FROM: Gregory H. Friedman Inspector General SUBJECT: INFORMATION: Special Report on "NNSA's Management of the $245 million Nuclear Materials Safeguards and Security Upgrades Project Phase II at Los Alamos National Laboratory" BACKGROUND The National Nuclear Security Administration's Los Alamos National Laboratory (LANL) is responsible for the protection and control of a significant portion of the Nation's special nuclear

427

SPRING DRIVEN ACTUATING MECHANISM FOR NUCLEAR REACTOR CONTROL  

DOE Patents (OSTI)

l962. rod in a nuclear reactor to shut it down. The control rod or an extension thereof is wound on a drum as it is withdrawn from the reactor. When an emergency occurs requiring the reactor to be shut down, the drum is released so as to be free to rotate, and the tendency of the control rod or its extension coiled on the drum to straighten itself is used for quickly returning the control rod to the reactor. (AEC)

Bevilacqua, F.; Uecker, D.F.; Groh, E.F.

1962-01-23T23:59:59.000Z

428

Materials for Nuclear Power: Digital Resource Center - REPORT ...  

Science Conference Proceedings (OSTI)

Feb 12, 2007 ... United States: Department of Energy Office of Nuclear Energy, Science, and Technology (NE) and the Office of Basic Energy Sciences (BES),...

429

Materials for Nuclear Power: Digital Resource Center Text Topic  

Science Conference Proceedings (OSTI)

Feb 12, 2007 ... United States: Department of Energy Office of Nuclear Energy, Science, and Technology (NE) and the Office of Basic Energy Sciences (BES),...

430

Materials for Nuclear Power: Digital Resource Center Text Topic  

Science Conference Proceedings (OSTI)

Feb 16, 2007 ... This site offers a comprehensive overview of the US Department of Energy's Office of Nuclear Physics' activities and research facilities.

431

Materials for Nuclear Power: Digital Resource Center Text Topic  

Science Conference Proceedings (OSTI)

Feb 12, 2007 ... CITATION: Technology and Applied R&D Needs for Advanced Nuclear Energy Systems, Office of Science, U. S. Department of Energy, June...

432

Materials for Nuclear Power: Digital Resource Center Text Topic  

Science Conference Proceedings (OSTI)

Jun 13, 2007 ... The Department of Energy (DOE)'s Office of Nuclear Energy held a workshop for universities on March 20, 2007, at the Gaithersburg Hilton...

433

Materials for Nuclear Power: Digital Resource Center - WEB ...  

Science Conference Proceedings (OSTI)

Jun 25, 2007 ... This web site provides an overview of the mission and activities of the US Nuclear Waste Technical Review Board. This independent federal...

434

Materials for Nuclear Power: Digital Resource Center - WEB ...  

Science Conference Proceedings (OSTI)

May 15, 2007 ... The Office of Environmental Management is responsible for the risk reduction and cleanup of the environmental legacy of the US nuclear...

435

Materials for Nuclear Power: Digital Resource Center Text Topic  

Science Conference Proceedings (OSTI)

Feb 19, 2007 ... This web site offers project overviews related to CEA's research into defense and security, nuclear energy, and other technologies.

436

Materials for Nuclear Power: Digital Resource Center Text Topic  

Science Conference Proceedings (OSTI)

Print this topic. Topic Title WEB RESOURCE: Nuclear Energy and Global Security Technologies Center. Date Posted: 5/15/2007 2:43 PM Posted By: Lynne...

437

Anode Materials for Reprocessing of Spent Nuclear Fuel  

Science Conference Proceedings (OSTI)

In order to consume current stockpiles, uranium dioxide spent nuclear fuel will be .... and Synthesis of Intermetallic Clathrates for Energy Storage and Recovery.

438

Materials for Nuclear Power: Digital Resource Center - WEB ...  

Science Conference Proceedings (OSTI)

Feb 19, 2007 ... Designed for high school students, this resource offers a brief introduction to nuclear physics through a variety of teaching tools, including...

439

Materials for Nuclear Power: Digital Resource Center -- Articles and ...  

Science Conference Proceedings (OSTI)

J. Lian, et. al., Journal of Applied Physics, 0, 322, Lynne Robinson ... Considerations for assessing the performance of nuclear waste repositories, 0, 385, Lynne...

440

Materials for Nuclear Power: Digital Resource Center - WEB ...  

Science Conference Proceedings (OSTI)

Feb 19, 2007 ... A primer on nuclear physics is also available. SOURCE: Wirth, Brian D. "NE24 - The Scientists of the Manhattan Project, their Contributions to...

Note: This page contains sample records for the topic "nuclear material control" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


441

Materials for Nuclear Power: Digital Resource Center - BOOK ... - TMS  

Science Conference Proceedings (OSTI)

Jun 22, 2007 ... Topic Title: BOOK: Scientific Basis for Nuclear Waste Management XXVII ... as papers on waste-, tank- and site-cleanup and decommissioning.

442

Materials for Nuclear Power: Digital Resource Center - WEB ... - TMS  

Science Conference Proceedings (OSTI)

May 15, 2007 ... This concise online guide to the nuclear fuel cycle offers a good overview of waste management and decommissioning processes. It is written...

443

Materials for Nuclear Power: Digital Resource Center - WEB ...  

Science Conference Proceedings (OSTI)

Jun 25, 2007 ... The U.S. Nuclear Regulatory Commission (NRC) was created as an ... Its regulatory mission covers three main areas: commercial reactors for...

444

Materials for Nuclear Power: Digital Resource Center - PDF: How ...  

Science Conference Proceedings (OSTI)

Oct 15, 2007 ... An overview presentation on "how nuclear reactors work", using the CANDU reactor design as an example. CITATION: Garland, W., "How and...

445

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

National Nuclear Security Administration (NNSA)

against both internal and external threat scenarios. OWMP is also oversees sustainability efforts at a number of nuclear sites in Ukraine, Kazakhstan, Uzbekistan, and...

446

Dilemmas of Nuclear Materials and Technology: From Los Alamos ...  

Science Conference Proceedings (OSTI)

In the form of nuclear weapons, governments have acquired the capacity to destroy civilization; on the other hand, in the form of electricity-generating plants, ...

447

A Potential Approach to Address Materials Aging Issues in Nuclear ...  

Science Conference Proceedings (OSTI)

Potential applications of this technology for nuclear reactor aystems will be ... First-Principles Theory of Magnetism, Crystal Field and Phonon Spectrum of UO2 .

448

Materials for Nuclear Power: Digital Resource Center - BOOK ...  

Science Conference Proceedings (OSTI)

Mar 28, 2007 ... This resource encapsulates an international forum, co-sponsored by TMS, the American Nuclear Society, and NACE, on the exchange of...

449

Materials for Nuclear Power: Digital Resource Center ... - TMS  

Science Conference Proceedings (OSTI)

ARTICLES: Global Nuclear Energy Partnership January 2008 JOM articles, 0, 883, Todd Osman, 1/4/2008 2:21 PM by Todd Osman. New Messages, Rating...

450

Materials for Nuclear Power: Digital Resource Center -- Sandbox  

Science Conference Proceedings (OSTI)

New Messages, Rating, 15th Int'l Conference on Environmental Degradation in Nuclear Power Systems Program Preview, 0, 1413, Patti Dobranski, 4/14/2011...

451

Materials for Nuclear Power: Digital Resource Center - WEB ...  

Science Conference Proceedings (OSTI)

Jun 13, 2007 ... The Department of Energy (DOE)'s Office of Nuclear Energy held a workshop for universities on March 20, 2007, at the Gaithersburg Hilton...

452

Materials for Nuclear Power: Digital Resource Center -- Web ...  

Science Conference Proceedings (OSTI)

Global Nuclear Energy Partnership (GNEP) DOE. Detailed information on the GNEP's implementing elements, 0, 761, Lynne Robinson, 6/22/2007 1:39 PM

453

Materials for Nuclear Power: Digital Resource Center - WEB ...  

Science Conference Proceedings (OSTI)

Dec 6, 2007 ... Nuclear power's prominence as a major energy source will continue over the next several decades, according to projections made by the...

454

Materials for Nuclear Power: Digital Resource Center - WEB ...  

Science Conference Proceedings (OSTI)

May 15, 2007 ... Access to forms and file codes is also provided. Citation: "Online Documents." Nuclear Energy and Global Security Technologies Center 2007.

455

Materials for Nuclear Power: Digital Resource Center - ARTICLE: On ...  

Science Conference Proceedings (OSTI)

May 25, 2007 ... The effect of the important chemical constiuents in the Hanford nuclear waste simulant on the anodic behavior of carbon steel was studied.

456

Corrosion and Mechanics of Materials - Nuclear Engineering Division...  

NLE Websites -- All DOE Office Websites (Extended Search)

Materials Testing Environmentally Assisted Cracking (EAC) of Reactor Materials Corrosion PerformanceMetal Dusting Overview Light Water Reactors Fossil Energy Fusion Energy...

457

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

Science Conference Proceedings (OSTI)

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 900C 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. Todays high-temperature alloys and associated ASME Codes for reactor applications are approved up to 760C. 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.

J. K. Wright

2008-04-01T23:59:59.000Z

458

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

SciTech Connect

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.

Menon, S.

2002-02-26T23:59:59.000Z

459

Dual annular rotating "windowed" nuclear reflector reactor control system  

DOE Patents (OSTI)

A nuclear reactor control system is provided in a nuclear reactor having a core operating in the fast neutron energy spectrum where criticality control is achieved by neutron leakage. The control system includes dual annular, rotatable reflector rings. There are two reflector rings: an inner reflector ring and an outer reflector ring. The reflectors are concentrically assembled, surround the reactor core, and each reflector ring includes a plurality of openings. The openings in each ring are capable of being aligned or non-aligned with each other. Independent driving means for each of the annular reflector rings is provided so that reactor criticality can be initiated and controlled by rotation of either reflector ring such that the extent of alignment of the openings in each ring controls the reflection of neutrons from the core.

Jacox, Michael G. (Idaho Falls, ID); Drexler, Robert L. (Idaho Falls, ID); Hunt, Robert N. M. (Idaho Falls, ID); Lake, James A. (Idaho Falls, ID)

1994-01-01T23:59:59.000Z

460

Advanced Test Reactor National Scientific User Facility: Addressing advanced nuclear materials research  

SciTech Connect

The Advanced Test Reactor National Scientific User Facility (ATR NSUF), based at the Idaho National Laboratory in the United States, is supporting Department of Energy and industry research efforts to ensure the properties of materials in light water reactors are well understood. The ATR NSUF is providing this support through three main efforts: establishing unique infrastructure necessary to conduct research on highly radioactive materials, conducting research in conjunction with industry partners on life extension relevant topics, and providing training courses to encourage more U.S. researchers to understand and address LWR materials issues. In 2010 and 2011, several advanced instruments with capability focused on resolving nuclear material performance issues through analysis on the micro (10-6 m) to atomic (10-10 m) scales were installed primarily at the Center for Advanced Energy Studies (CAES) in Idaho Falls, Idaho. These instruments included a local electrode atom probe (LEAP), a field-emission gun scanning transmission electron microscope (FEG-STEM), a focused ion beam (FIB) system, a Raman spectrometer, and an nanoindentor/atomic force microscope. Ongoing capability enhancements intended to support industry efforts include completion of two shielded, irradiation assisted stress corrosion cracking (IASCC) test loops, the first of which will come online in early calendar year 2013, a pressurized and controlled chemistry water loop for the ATR center flux trap, and a dedicated facility intended to house post irradiation examination equipment. In addition to capability enhancements at the main site in Idaho, the ATR NSUF also welcomed two new partner facilities in 2011 and two new partner facilities in 2012; the Oak Ridge National Laboratory, High Flux Isotope Reactor (HFIR) and associated hot cells and the University California Berkeley capabilities in irradiated materials analysis were added in 2011. In 2012, Purdue Universitys Interaction of Materials with Particles and Components Testing (IMPACT) facility and the Pacific Northwest Nuclear Laboratory (PNNL) Radiochemistry Processing Laboratory (RPL) and PIE facilities were added. The ATR NSUF annually hosts a weeklong event called Users Week in which students and faculty from universities as well as other interested parties from regulatory agencies or industry convene in Idaho Falls, Idaho to see presentations from ATR NSUF staff as well as select researchers from the materials research field. Users week provides an overview of current materials research topics of interest and an opportunity for young researchers to understand the process of performing work through ATR NSUF. Additionally, to increase the number of researchers engaged in LWR materials issues, a series of workshops are in progress to introduce research staff to stress corrosion cracking, zirconium alloy degradation, and uranium dioxide degradation during in-reactor use.

John Jackson; Todd Allen; Frances Marshall; Jim Cole

2013-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear material control" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


461

Some thoughts on the nonproliferation of nuclear weapons  

Science Conference Proceedings (OSTI)

This paper discusses factors controlling the dissemination of nuclear technologies and especially fissile materials.

Krikorian N.H.; Hawkins, H.T.

1996-05-01T23:59:59.000Z

462

A Busy Year Securing Vulnerable Nuclear Material and Making the World Safer  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

A Busy Year Securing Vulnerable Nuclear Material and Making the A Busy Year Securing Vulnerable Nuclear Material and Making the World Safer A Busy Year Securing Vulnerable Nuclear Material and Making the World Safer January 7, 2011 - 6:22pm Addthis John Schueler John Schueler Former New Media Specialist, Office of Public Affairs This holiday season was certainly a busy one for the National Nuclear Security Administration (NNSA). While many Americans were off completing last minute Christmas shopping and spending time with loved ones, the team at NNSA was working around the clock to secure over 50 kilograms of highly enriched uranium from three sites in the Ukraine. As part of President Obama's ambitious plan to secure all vulnerable nuclear material around the world in four years, NNSA assisted in repatriating the dangerous

463

EA-1954: Resumption of Transient Testing of Nuclear Fuels and Materials at  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

4: Resumption of Transient Testing of Nuclear Fuels and 4: Resumption of Transient Testing of Nuclear Fuels and Materials at the Idaho National Laboratory, Idaho EA-1954: Resumption of Transient Testing of Nuclear Fuels and Materials at the Idaho National Laboratory, Idaho SUMMARY 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. PUBLIC COMMENT OPPORTUNITIES DOE invites the public to read and comment on a draft environmental assessment it has prepared for a proposal to resume transient testing of nuclear fuels and materials at either Idaho National Laboratory or Sandia

464

Next Generation Nuclear Plant Resilient Control System Functional Analysis  

SciTech Connect

Control Systems and their associated instrumentation must meet reliability, availability, maintainability, and resiliency criteria in order for high temperature gas-cooled reactors (HTGRs) to be economically competitive. Research, perhaps requiring several years, may be needed to develop control systems to support plant availability and resiliency. This report functionally analyzes the gaps between traditional and resilient control systems as applicable to HTGRs, which includes the Next Generation Nuclear Plant; defines resilient controls; assesses the current state of both traditional and resilient control systems; and documents the functional gaps existing between these two controls approaches as applicable to HTGRs. This report supports the development of an overall strategy for applying resilient controls to HTGRs by showing that control systems with adequate levels of resilience perform at higher levels, respond more quickly to disturbances, increase operational efficiency, and increase public protection.

Lynne M. Stevens

2010-07-01T23:59:59.000Z

465

Kinetic advantage of controlled intermediate nuclear fusion  

SciTech Connect

The dominated process of controlled fusion is to let nuclei gain enough kinetic energy to overcome Coulomb barrier. As a result, a fusion scheme can consider two factors in its design: to increase kinetic energy of nuclei and to alter the Coulomb barrier. Cold Fusion and Hot fusion are all one-factor schemes while Intermediate Fusion is a twofactors scheme. This made CINF kinetically superior. Cold Fusion reduces deuteron-deuteron distance, addressing Coulomb barrier, and Hot Fusion heat up plasma into extreme high temperature, addressing kinetic energy. Without enough kinetic energy made Cold Fusion skeptical. Extreme high temperature made Hot Fusion very difficult to engineer. Because CIFN addresses both factors, CIFN is a more promising technique to be industrialized.

Guo Xiaoming [Physics and Computer Science Department, Wilfrid Laurier University, Waterloo, Ontario, N2L 3C5 (Canada)

2012-09-26T23:59:59.000Z

466

Materials for Nuclear Power: Digital Resource Center - WEB ...  

Science Conference Proceedings (OSTI)

Jul 6, 2007 ... The link provided leads to the nuclear waste storage section of a larger study, published in 2001, on the impact of metallic corrosion on the US...

467

Formation of new materials in fullerenes by using nuclear recoil  

Science Conference Proceedings (OSTI)

The formation of Sb or Te atom-incorporated fullerenes has been investigated by using radionuclides produced by nuclear reactions. From the trace of radioactivities of 120 Sb( 122 Sb) or 121 Te after High Pressure Liquid Chromatography (HPLC)

T. Ohtsuki; K. Ohno; K. Shiga; Y. Kawazoe; Y. Maruyama; K. Shikano; K. Masumoto

2001-01-01T23:59:59.000Z

468

Materials for Nuclear Power: Digital Resource Center - REPORT ...  

Science Conference Proceedings (OSTI)

Jun 27, 2007... Fate of the Epsilon Phase in UO2 of the Oklo Natural Fisson Reactors ... In spent nuclear fuel (SNF), the micron- to nano-sized epsilon phase...

469

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

National Nuclear Security Administration (NNSA)

located in closed cities. In some cases, these industrial sites are the size of small cities and contain hundreds of metric tons of highly attractive weapons-usable nuclear...

470

Human error contribution to nuclear materials-handling events  

E-Print Network (OSTI)

This thesis analyzes a sample of 15 fuel-handling events from the past ten years at commercial nuclear reactors with significant human error contributions in order to detail the contribution of human error to fuel-handling ...

Sutton, Bradley (Bradley Jordan)

2007-01-01T23:59:59.000Z

471

Metal Dusting [Corrosion and Mechanics of Materials] - Nuclear...  

NLE Websites -- All DOE Office Websites (Extended Search)

Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Corrosion and Mechanics of Materials Metal Dusting Bookmark and Share R&D 100 AWARD The "Materials resistant...

472

Russia-U.S. joint program on the safe management of nuclear materials  

Science Conference Proceedings (OSTI)

The Russia-US joint program on the safe management of nuclear materials was initiated to address common technical issues confronting the US and Russia in the management of excess weapons grade nuclear materials. The program was initiated after the 1993 Tomsk-7 accident. This paper provides an update on program activities since 1996. The Fourth US Russia Nuclear Materials Safety Management Workshop was conducted in March 1997. In addition, a number of contracts with Russian Institutes have been placed by Lawrence Livermore National Laboratory (LLNL) and Sandia National Laboratories (SNL). These contracts support research related to the safe disposition of excess plutonium (Pu) and highly enriched uranium (HEU). Topics investigated by Russian scientists under contracts with SNL and LLNL include accident consequence studies, the safety of anion exchange processes, underground isolation of nuclear materials, and the development of materials for the immobilization of excess weapons Pu.

Witmer, F.E.; Krumpe, P.F. [Dept. of Energy, Washington, DC (United States); Carlson, D.D. [Sandia National Labs., Albuquerque, NM (United States)] [and others

1998-06-01T23:59:59.000Z

473

Materials for Nuclear Power: Digital Resource Center Text Topic  

Science Conference Proceedings (OSTI)

Feb 19, 2007 ... Print this topic. Topic Title WEB RESOURCE: Office of Fusion Energy Sciences, Materials Science Program...

474

Introduction to Nuclear Plant Steam Turbine Control Systems  

Science Conference Proceedings (OSTI)

Since Nuclear Power Plants produce their power through the use of Steam Turbine Generators, any problems associated with the Turbine Control System has a direct effect on power generation. Although considerable effort has been expended in improving control system reliability, failures resulting in lost generation and high maintenance cost still plague the industry. On an individual basis, improvements have been made through maintenance techniques, modifications and upgrades. Unfortunately, this informati...

1995-03-02T23:59:59.000Z

475

Method of controlling crystallite size in nuclear-reactor fuels  

DOE Patents (OSTI)

Improved spherules for making enhanced forms of nuclear-reactor fuels are prepared by internal gelation procedures within a sol-gel operation and are accomplished by first boiling the concentrated HMTA-urea feed solution before engaging in the spherule-forming operation thereby effectively controlling crystallite size in the product spherules.

Lloyd, Milton H. (Oak Ridge, TN); Collins, Jack L. (Knoxville, TN); Shell, Sam E. (Oak Ridge, TN)

1985-01-01T23:59:59.000Z

476

Automatic coolant flow control device for a nuclear reactor assembly  

DOE Patents (OSTI)

A device which controls coolant flow through a nuclear reactor assembly comprises a baffle means at the exit end of said assembly having a plurality of orifices, and a bimetallic member in operative relation to the baffle means such that at increased temperatures said bimetallic member deforms to unblock some of said orifices and allow increased coolant flow therethrough.

Hutter, Ernest (Wilmette, IL)

1986-01-01T23:59:59.000Z

477

Automatic coolant flow control device for a nuclear reactor assembly  

DOE Patents (OSTI)

A device which controls coolant flow through a nuclear reactor assembly comprises a baffle means at the exit end of said assembly having a plurality of orifices, and a bimetallic member in operative relation to the baffle means such that at increased temperatures said bimetallic member deforms to unblock some of said orifices and allow increased coolant flow therethrough.

Hutter, E.

1984-01-27T23:59:59.000Z

478

Adaptive nuclear reactor control for integral quadratic cost functions  

Science Conference Proceedings (OSTI)

The problem of optimally controlling the power level changes of a nuclear reactor is considered. The model of an existing power plant is used, which is a ninth-order nonlinear system, having time-varying parameters. A closed form solution of the optimal ...

George T. Bereznai; Naresh K. Sinha

1973-09-01T23:59:59.000Z

479

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

DOE Patents (OSTI)

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.

Norman, Eric B. (Oakland, CA); Prussin, Stanley G. (Kensington, CA)

2007-10-02T23:59:59.000Z

480

Indicator system for advanced nuclear plant control complex  

DOE Patents (OSTI)

An advanced control room complex for a nuclear power plant, including a discrete indicator and alarm system (72) which is nuclear qualified for rapid response to changes in plant parameters and a component control system (64) which together provide a discrete monitoring and control capability at a panel (14-22, 26, 28) in the control room (10). A separate data processing system (70), which need not be nuclear qualified, provides integrated and overview information to the control room and to each panel, through CRTs (84) and a large, overhead integrated process status overview board (24). The discrete indicator and alarm system (72) and the data processing system (70) receive inputs from common plant sensors and validate the sensor outputs to arrive at a representative value of the parameter for use by the operator during both normal and accident conditions, thereby avoiding the need for him to assimilate data from each sensor individually. The integrated process status board (24) is at the apex of an information hierarchy that extends through four levels and provides access at each panel to the full display hierarchy. The control room panels are preferably of a modular construction, permitting the definition of inputs and outputs, the man machine interface, and the plant specific algorithms, to proceed in parallel with the fabrication of the panels, the installation of the equipment and the generic testing thereof.

Scarola, Kenneth (Windsor, CT); Jamison, David S. (Windsor, CT); Manazir, Richard M. (North Canton, CT); Rescorl, Robert L. (Vernon, CT); Harmon, Daryl L. (Enfield, CT)

1993-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "nuclear material control" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


481

Electromagnetic valve for controlling the flow of molten, magnetic material  

DOE Patents (OSTI)

An electromagnetic valve for controlling the flow of molten, magnetic material is provided, which comprises an induction coil for generating a magnetic field in response to an applied alternating electrical current, a housing, and a refractory composite nozzle. The nozzle is comprised of an inner sleeve composed of an erosion resistant refractory material (e.g., a zirconia ceramic) through which molten, magnetic metal flows, a refractory outer shell, and an intermediate compressible refractory material, e.g., unset, high alumina, thermosetting mortar. The compressible refractory material is sandwiched between the inner sleeve and outer shell, and absorbs differential expansion stresses that develop within the nozzle due to extreme thermal gradients. The sandwiched layer of compressible refractory material prevents destructive cracks from developing in the refractory outer shell.

Richter, Tomas (State College, PA)

1998-01-01T23:59:59.000Z

482

Electromagnetic valve for controlling the flow of molten, magnetic material  

DOE Patents (OSTI)

An electromagnetic valve for controlling the flow of molten, magnetic material is provided, which comprises an induction coil for generating a magnetic field in response to an applied alternating electrical current, a housing, and a refractory composite nozzle. The nozzle is comprised of an inner sleeve composed of an erosion resistant refractory material (e.g., a zirconia ceramic) through which molten, magnetic metal flows, a refractory outer shell, and an intermediate compressible refractory material, e.g., unset, high alumina, thermosetting mortar. The compressible refractory material is sandwiched between the inner sleeve and outer shell, and absorbs differential expansion stresses that develop within the nozzle due to extreme thermal gradients. The sandwiched layer of compressible refractory material prevents destructive cracks from developing in the refractory outer shell. 5 figs.

Richter, T.

1998-06-16T23:59:59.000Z

483

Improved Design of Nuclear Reactor Control System | U.S. DOE...  

Office of Science (SC) Website

Improved Design of Nuclear Reactor Control System Nuclear Physics (NP) NP Home About Research Facilities Science Highlights Benefits of NP Spinoff Applications Spinoff Archives...

484

A Latent Model to Detect Multiple Spatial Clusters with Application in a Mobile Sensor Network for Surveillance of Nuclear Materials  

E-Print Network (OSTI)

surveillance of nuclear materials in major cities. The network consists of a large number of vehicles on which for Surveillance of Nuclear Materials Jerry Cheng, Minge Xie, Rong Chen and Fred Roberts1 Abstract Nuclear attacks to infrastructure. To deter such threats, it becomes increasingly vital to have sophisticated nuclear surveillance

485

Materials and Sensor R&D to Transform the Nuclear Stockpile: Livermore?s Transformational Materials Initiative  

DOE Green Energy (OSTI)

As the nation's nuclear weapons age and the demands placed on them change, significant challenges face the nuclear stockpile. Risks include