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Note: This page contains sample records for the topic "disposition radioactive materials" 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

THE NGA-DOE GRANT TO EXAMINE CRITICAL ISSUES RELATED TO RADIOACTIVE WASTE AND MATERIALS DISPOSITION INVOLVING DOE FACILITIES  

Science Conference Proceedings (OSTI)

Through the National Governors' Association (NGA) project ''Critical Issues Related to Radioactive Waste and Materials Disposition Involving DOE Facilities'' NGA brings together Governors' policy advisors, state regulators, and DOE officials to examine critical issues related to the cleanup and operation of DOE nuclear weapons and research facilities. Topics explored through this project include: Decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials. Decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities. Strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex. Changes to the FFCA site treatment plans as a result of proposals in the Department's Accelerating Cleanup: Paths to Closure plan and contractor integration analysis. Interstate waste and materials shipments. Reforms to existing RCRA and CERCLA regulations/guidance to address regulatory overlap and risks posed by DOE wastes. The overarching theme of this project is to help the Department improve coordination of its major program decisions with Governors' offices and state regulators and to ensure such decisions reflect input from these key state officials and stakeholders. This report summarizes activities conducted during the period from April 1, 2001 through June 30, 2001, under the NGA grant.

Ethan W. Brown

2001-09-01T23:59:59.000Z

2

THE NGA-DOE GRANT TO EXAMINE CRITICAL ISSUES RELATED TO RADIOACTIVE WASTE AND MATERIALS DISPOSITION INVOLVING DOE FACILITIES  

SciTech Connect

Through the National Governors' Association (NGA) project ''Critical Issues Related to Radioactive Waste and Materials Disposition Involving DOE Facilities'' NGA brings together Governors' policy advisors, state regulators, and DOE officials to examine critical issues related to the cleanup and operation of DOE nuclear weapons and research facilities. Topics explored through this project include: Decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials; Decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities; Strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex; Changes to the FFCA site treatment plans as a result of proposals in the Department's Accelerating Cleanup: Paths to Closure plan and contractor integration analysis; Interstate waste and materials shipments; and Reforms to existing RCRA and CERCLA regulations/guidance to address regulatory overlap and risks posed by DOE wastes. The overarching theme of this project is to help the Department improve coordination of its major program decisions with Governors' offices and state regulators and to ensure such decisions reflect input from these key state officials and stakeholders. This report summarizes activities conducted during the quarter from May 1, 1999, through July 30, 1999, under the NGA grant. The work accomplished by the NGA project team during the past four months can be categorized as follows: maintained open communication with DOE on a variety of activities and issues within the DOE environmental management complex; maintained communication with NGA Federal Facilities Compliance Task Force members regarding DOE efforts to formulate a configuration for mixed low-level waste and low-level treatment and disposal, external regulation of DOE; and continued to facilitate interactions between the states and DOE to develop a foundation for an ongoing substantive relationship between the Governors of key states and Secretary Richardson.

Ann M. Beauchesne

1999-07-30T23:59:59.000Z

3

THE NGA-DOE GRANT TO EXAMINE CRITICAL ISSUES RELATED TO RADIOACTIVE WASTE AND MATERIALS DISPOSITION INVOLVING DOE FACILITIES  

Science Conference Proceedings (OSTI)

Through the National Governors' Association (NGA) project ''Critical Issues Related to Radioactive Waste and Materials Disposition Involving DOE Facilities'' NGA brings together Governors' policy advisors, state regulators, and DOE officials to examine critical issues related to the cleanup and operation of DOE nuclear weapons and research facilities. Topics explored through this project include: Decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials; Decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities; Strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex; Changes to the FFCA site treatment plans as a result of proposals in the Department's Accelerating Cleanup: Paths to Closure plan and contractor integration analysis; Interstate waste and materials shipments; and Reforms to existing RCRA and CERCLA regulations/guidance to address regulatory overlap and risks posed by DOE wastes. The overarching theme of this project is to help the Department improve coordination of its major program decisions with Governors' offices and state regulators and to ensure such decisions reflect input from these key state officials and stakeholders. This report summarizes activities conducted during the quarter from February 1, 1999, through April 30, 1999, under the NGA grant. The work accomplished by the NGA project team during the past four months can be categorized as follows: maintained open communication with DOE on a variety of activities and issues within the DOE environmental management complex; maintained communication with NGA Federal Facilities Compliance Task Force members regarding DOE efforts to formulate a configuration for mixed low-level waste and low-level treatment and disposal, external regulation of DOE; and EM Integration activities; and continued to serve as a liaison between the NGA FFCA Task Force states and the Department.

Ann M. Beauchesne

1999-04-30T23:59:59.000Z

4

THE NGA-DOE GRANT TO EXAMINE CRITICAL ISSUES RELATED TO RADIOACTIVE WASTE AND MATERIALS DISPOSITION INVOLVING DOE FACILITIES  

SciTech Connect

Through the National Governors' Association (NGA) project ''Critical Issues Related to Radioactive Waste and Materials Disposition Involving DOE Facilities'' NGA brings together Governors' policy advisors, state regulators, and DOE officials to examine critical issues related to the cleanup and operation of DOE nuclear weapons and research facilities. Topics explored through this project include: Decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials. Decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities. Strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex. Changes to the FFCA site treatment plans as a result of proposals in DOE's Accelerating Cleanup: Paths to Closure strategy and contractor integration analysis. Interstate waste and materials shipments. Reforms to existing RCRA and CERCLA regulations/guidance to address regulatory overlap and risks posed by DOE wastes. The overarching theme of this project is to help the Department improve coordination of its major program decisions with Governors' offices and state regulators and to ensure such decisions reflect input from these key state officials and stakeholders. This report summarizes activities conducted during the quarter from December 31, 1997 through April 30, 1998 under the NGA project. The work accomplished by the NGA project team during the past four months can be categorized as follows: maintained open communication with DOE on a variety of activities and issues within the DOE environmental management complex; and provided ongoing support to state-DOE interactions in preparation for the March 30-31, 1998 NGA Federal Facilities Compliance Task Force Meeting with DOE. maintained communication with NGA Federal Facilities Compliance Task Force members regarding DOE efforts to formulate a configuration for mixed low-level waste and low-level treatment and disposal, DOE's Environmental Management Budget, and DOE's proposed Intersite Discussions.

NONE

1998-04-01T23:59:59.000Z

5

THE NGA-DOE GRANT TO EXAMINE CRITICAL ISSUES RELATED TO RADIOACTIVE WASTE AND MATERIALS DISPOSITION INVOLVING DOE FACILITIES  

SciTech Connect

Through the National Governors Association (NGA) project ``Critical Issues Related to Radioactive Waste and Materials Disposition Involving DOE Facilities'' NGA brings together Governors' policy advisors, state regulators, and DOE officials to examine critical issues related to the cleanup and operation of DOE nuclear weapons and research facilities. Topics explored through this project include: Decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials; Decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities; Strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex; Changes to the FFCA site treatment plans as a result of proposals in the Department's Accelerating Cleanup: Paths to Closure plan and contractor integration analysis; Interstate waste and materials shipments; and Reforms to existing RCRA and CERCLA regulations/guidance to address regulatory overlap and risks posed by DOE wastes. The overarching theme of this project is to help the Department improve coordination of its major program decisions with Governors' offices and state regulators and to ensure such decisions reflect input from these key state officials and stakeholders. This report summarizes activities conducted during the period from October 1, 1999 through January 31, 2000, under the NGA grant. The work accomplished by the NGA project team during the past three months can be categorized as follows: maintained open communication with DOE on a variety of activities and issues within the DOE environmental management complex; convened and facilitated the October 6--8 NGA FFCA Task Force Meeting in Oak Ridge, Tennessee; maintained communication with NGA Federal Facilities Compliance Task Force members regarding DOE efforts to formulate a configuration for mixed low-level waste and low-level treatment and disposal, external regulation of DOE; and continued to facilitate interactions between the states and DOE to develop a foundation for an ongoing substantive relationship between the Governors of key states and the Department.

Ann M. Beauchesne

2000-01-01T23:59:59.000Z

6

THE NGA-DOE GRANT TO EXAMINE CRITICAL ISSUES RELATED TO RADIOACTIVE WASTE AND MATERIALS DISPOSITION INVOLVING DOE FACILITIES  

Science Conference Proceedings (OSTI)

Through the National Governors' Association (NGA) project ''Critical Issues Related to Radioactive Waste and Materials Disposition Involving DOE Facilities'' NGA brings together Governors' policy advisors, state regulators, and DOE officials to examine critical issues related to the cleanup and operation of DOE nuclear weapons and research facilities. Topics explored through this project include: Decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials. Decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities. Strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex. Changes to the FFCA site treatment plans as a result of proposals in DOE's Accelerating Cleanup: Paths to Closure strategy and contractor integration analysis. Interstate waste and materials shipments. Reforms to existing RCRA and CERCLA regulations/guidance to address regulatory overlap and risks posed by DOE wastes. The overarching theme of this project is to help the Department improve coordination of its major program decisions with Governors' offices and state regulators and to ensure such decisions reflect input from these key state officials and stakeholders. This report summarizes activities conducted during the quarter from April 30, 1998 through June 30, 1998 under the NGA project. The work accomplished by the NGA project team during the past four months can be categorized as follows: maintained open communication with DOE on a variety of activities and issues within the DOE environmental management complex; and provided ongoing support to state-DOE interactions. maintained communication with NGA Federal Facilities Compliance Task Force members regarding DOE efforts to formulate a configuration for mixed low-level waste and low-level treatment and disposal, DOE's Environmental Management Budget, and DOE's proposed Intersite Discussions.

NONE

1998-07-01T23:59:59.000Z

7

THE NGA-DOE GRANT TO EXAMINE CRITICAL ISSUES RELATED TO RADIOACTIVE WASTE AND MATERIALS DISPOSITION INVOLVING DOE FACILITIES  

Science Conference Proceedings (OSTI)

Through the National Governors' Association (NGA) project ''Critical Issues Related to Radioactive Waste and Materials Disposition Involving DOE Facilities'' NGA brings together Governors' policy advisors, state regulators, and DOE officials to examine critical issues related to the cleanup and operation of DOE nuclear weapons and research facilities. Topics explored through this project include: (1) Decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials; (2) Decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities; (3) Strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex; (4) Changes to the FFCA site treatment plans as a result of proposals in the Department's Accelerating Cleanup: Paths to Closure plan and contractor integration analysis; (5) Interstate waste and materials shipments; and (6) Reforms to existing RCRA and CERCLA regulations/guidance to address regulatory overlap and risks posed by DOE wastes. The overarching theme of this project is to help the Department improve coordination of its major program decisions with Governors' offices and state regulators and to ensure such decisions reflect input from these key state officials and stakeholders. This report summarizes activities conducted during the quarter from October 1, 1998 through January 31, 1999, under the NGA grant. The work accomplished by the NGA project team during the past four months can be categorized as follows: (1) maintained open communication with DOE on a variety of activities and issues within the DOE environmental management complex; (2) maintained communication with NGA Federal Facilities Compliance Task Force members regarding DOE efforts to formulate a configuration for mixed low-level waste and low-level treatment and disposal, external regulation of DOE; and EM Integration activities; and (3) continued to serve as a liaison between the NGA FFCA Task Force states and the Department.

Ann M. Beauchesne

1999-01-31T23:59:59.000Z

8

THE NGA-DOE GRANT TO EXAMINE CRITICAL ISSUES RELATED TO RADIOACTIVE WASTE AND MATERIALS DISPOSITION INVOLVING DOE FACILITIES  

SciTech Connect

Through the National Governors' Association (NGA) project ''Critical Issues Related to Radioactive Waste and Materials Disposition Involving DOE Facilities'' NGA brings together Governors' policy advisors, state regulators, and DOE officials to examine critical issues related to the cleanup and operation of DOE nuclear weapons and research facilities. Topics explored through this project include: (1) Decisions involving disposal of mixed, low-level, and transuranic (TRU) waste and disposition of nuclear materials; (2) Decisions involving DOE budget requests and their effect on environmental cleanup and compliance at DOE facilities; (3) Strategies to treat mixed, low-level, and transuranic (TRU) waste and their effect on individual sites in the complex; (4) Changes to the FFCA site treatment plans as a result of proposals in the Department's Accelerating Cleanup: Paths to Closure plan and contractor integration analysis; (5) Interstate waste and materials shipments; and (6) Reforms to existing RCRA and CERCLA regulations/guidance to address regulatory overlap and risks posed by DOE wastes. The overarching theme of this project is to help the Department improve coordination of its major program decisions with Governors' offices and state regulators and to ensure such decisions reflect input from these key state officials and stakeholders. This report summarizes activities conducted during the quarter from June 1, 1998 through September 30, 1998, under the NGA grant. The work accomplished by the NGA project team during the past four months can be categorized as follows: (1) maintained open communication with DOE on a variety of activities and issues within the DOE environmental management complex; (2) maintained communication with NGA Federal Facilities Compliance Task Force members regarding DOE efforts to formulate a configuration for mixed low-level waste and low-level treatment and disposal, external regulation of DOE; and EM Integration activities; and (3) continued to serve as a liaison between the NGA FFCA Task Force states and the Department.

Ann B. Beauchesne

1998-09-30T23:59:59.000Z

9

EA-1599: Disposition of Radioactively Contaminated Nickel Located at the  

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

99: Disposition of Radioactively Contaminated Nickel Located 99: Disposition of Radioactively Contaminated Nickel Located at the East Tennessee Technology Park, Oak Ridge, Tennessee, and the Paducah Gaseous Diffusion Plant, Paducah, Kentucky, for Controlled Radiological Applications EA-1599: Disposition of Radioactively Contaminated Nickel Located at the East Tennessee Technology Park, Oak Ridge, Tennessee, and the Paducah Gaseous Diffusion Plant, Paducah, Kentucky, for Controlled Radiological Applications Summary This EA was being prepared to evaluate potential environmental impacts of a proposal to dispose of nickel scrap that is volumetrically contaminated with radioactive materials and that DOE recovered from equipment it had used in uranium enrichment. This EA is on hold. Public Comment Opportunities No public comment opportunities at this time.

10

Waste and Materials Disposition Information | Department of Energy  

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

Waste and Materials Disposition Waste and Materials Disposition Information Waste and Materials Disposition Information Waste and Materials Disposition Information As the Office of Environmental Management (EM) fulfills its mission, waste and materials disposition plays a vital role in the cleanup of radioactive waste and the environmental legacy of nuclear weapons production and nuclear energy research. Disposal of waste frequently falls on the critical path of cleanup projects. Significant planning resources are spent to identify alternatives and find a path that is cost-effective and in the best interest of the Federal government. In many instances, waste disposition, (processing, treatment and disposal) is part of cleanup agreements and is of interest to stakeholders and requires the oversight of regulators.

11

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

12

EM Waste and Materials Disposition & Transportation  

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

On Closure Success On Closure Success 1 EM Waste and Materials Disposition & Transportation National Transportation Stakeholders Forum Chicago, Illinois May 26, 2010 Frank Marcinowski Acting Chief Technical Officer and Deputy Assistant Secretary for Technical and Regulatory Support Office of Environmental Management DOE's Radioactive Waste Management Priorities * Continue to manage waste inventories in a safe and compliant manner * Address high risk waste in a cost- ff ti effective manner * Maintain and optimize current disposal capability for future generations * Develop future disposal capacity in a complex environment * Promote the development of treatment and disposal alternatives in the 2 and disposal alternatives in the

13

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...

14

EM Waste and Materials Disposition & Transportation | Department...  

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

and disposal alternatives in the 2 commercial sector Review current policies and directives Provide needed oversight EM Waste and Materials Disposition & Transportation More...

15

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

16

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...

17

Disposition of excess fissile materials in deep boreholes  

SciTech Connect

As a result of recent changes throughout the world, a substantial inventory of excess separated plutonium is expected to result from dismantlement of US nuclear weapons. The safe and secure management and eventual disposition of this plutonium, and of a similar inventory in Russia, is a high priority. A variety of options (both interim and permanent) are under consideration to manage this material. The permanent solutions can be categorized into two broad groups: direct disposal and utilization. Plutonium utilization options have in common the generation of high-level radioactive waste which will be disposed of in a mined geologic disposal system to be developed for spent reactor fuel and defense high level waste. Other final disposition forms, such as plutonium metal, plutonium oxide and plutonium immobilized without high-level radiation sources may be better suited to placement in a custom facility. This paper discusses a leading candidate for such a facility; deep (several kilometer) borehole disposition. The deep borehole disposition concept involves placing excess plutonium deep into old stable rock formations with little free water present. The safety argument centers around ancient groundwater indicating lack of migration, and thus no expected communication with the accessible environment until the plutonium has decayed.

Halsey, W.G. [Lawrence Livermore National Lab., CA (United States); Danker, W. [USDOE, Washington, DC (United States); Morley, R. [Los Alamos National Lab., NM (United States)

1995-09-01T23:59:59.000Z

18

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.

19

Midwestern Radioactive Materials Transportation Committee Agenda...  

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

Midwestern Radioactive Materials Transportation Committee Agenda Midwestern Radioactive Materials Transportation Committee Agenda Midwestern Radioactive Materials Transportation...

20

``Cats and Dogs'' disposition at Sandia: Last of the legacy materials  

SciTech Connect

Over the past 12 months, Sandia National Laboratories, New Mexico (SNL/NM), has successfully conducted an evaluation of its nuclear material holdings. As a result, approximately 46% of these holdings (36% by mass) have been reclassified as no defined use (NDU). Reclassification as NDU allows Sandia to determine the final disposition of a significant percentage of its legacy nuclear material. Disposition will begin some time in mid CY2000. This reclassification and the proposed disposition of the material has resulted in an extensive coordination effort lead by the Nuclear Materials Management Team (NMMT), which includes the nuclear material owners, the Radioactive Waste/Nuclear Material Disposition Department (7135), and DOE Albuquerque Operations Office. The process of identifying and reclassifying the cats and dogs or miscellaneous lots of nuclear material has also presented a number of important lessons learned for other sites in the DOE complex.

STRONG,WARREN R.; JACKSON,JOHN L.

2000-05-03T23:59:59.000Z

Note: This page contains sample records for the topic "disposition radioactive materials" 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

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...

22

Proliferation resistance criteria for fissile material disposition issues  

Science Conference Proceedings (OSTI)

The 1994 National Acdaemy of Sciences study ``Management and Disposition of Excess Weapons Plutonium`` defined options for reducing the national and international proliferation risks of materials declared excess to the nuclear weapons program. This paper proposes criteria for assessing the proliferation resistance of these options as well defining the ``Standards`` from the report. The criteria are general, encompassing all stages of the disposition process from storage through intermediate processing to final disposition including the facilities, processing technologies and materials, the level of safeguards for these materials, and the national/subnational threat to the materials.

Rutherford, D.A.; Fearey, B.L.; Markin, J.T.; Close, D.A. [Los Alamos National Lab., NM (United States); Tolk, K.M.; Mangan, D.L. [Sandia National Labs., Albuquerque, NM (United States); Moore, L. [Lawrence Livermore National Lab., CA (United States)

1995-09-01T23:59:59.000Z

23

Container for radioactive materials  

DOE Patents (OSTI)

A container for housing a plurality of canister assemblies containing radioactive material and disposed in a longitudinally spaced relation within a carrier to form a payload package concentrically mounted within the container. The payload package includes a spacer for each canister assembly, said spacer comprising a base member longitudinally spacing adjacent canister assemblies from each other and a sleeve surrounding the associated canister assembly for centering the same and conducting heat from the radioactive material in a desired flow path.

Fields, Stanley R. (Richland, WA)

1985-01-01T23:59:59.000Z

24

Container for radioactive materials  

DOE Patents (OSTI)

A container is claimed for housing a plurality of canister assemblies containing radioactive material. The several canister assemblies are stacked in a longitudinally spaced relation within a carrier to form a payload concentrically mounted within the container. The payload package includes a spacer for each canister assembly, said spacer comprising a base member longitudinally spacing adjacent canister assemblies from each other and sleeve surrounding the associated canister assembly for centering the same and conducting heat from the radioactive material in a desired flow path. 7 figures.

Fields, S.R.

1984-05-30T23:59:59.000Z

25

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...

26

LCA Carbon Footprints Mining Materials Mfg Transport Use Disposition  

E-Print Network (OSTI)

LCA Carbon Footprints #12;Mining Materials Mfg Transport Use Disposition Recycle Transporta;on Use End of Life Results: Yours Six Products, Six Carbon Footprints, WSJ, 2009 Transporta;on Use End of Life Results: Yours Six Products, Six Carbon Footprints, WSJ, 2009

Gutowski, Timothy

27

Logistics planning under uncertainty for disposition of radioactive wastes  

Science Conference Proceedings (OSTI)

The US Department of Energy (DOE) faces an enormous environmental remediation challenge involving highly radioactive wastes at former weapons production facilities. The purpose of this analysis is to focus on equipment acquisition and fleet sizing issues ...

George F. List; Bryan Wood; Mark A. Turnquist; Linda K. Nozick; Dean A. Jones; Craig R. Lawton

2006-03-01T23:59:59.000Z

28

Plutonium Disposition Program | National Nuclear Security Administrati...  

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

Plutonium Disposition Program Home > About Us > Our Programs > Nonproliferation > Fissile Materials Disposition > Plutonium Disposition Program Plutonium Disposition Program The...

29

Radioactive waste material melter apparatus  

DOE Patents (OSTI)

An apparatus for preparing metallic radioactive waste material for storage is disclosed. The radioactive waste material is placed in a radiation shielded enclosure. The waste material is then melted with a plasma torch and cast into a plurality of successive horizontal layers in a mold to form a radioactive ingot in the shape of a spent nuclear fuel rod storage canister. The apparatus comprises a radiation shielded enclosure having an opening adapted for receiving a conventional transfer cask within which radioactive waste material is transferred to the apparatus. A plasma torch is mounted within the enclosure. A mold is also received within the enclosure for receiving the melted waste material and cooling it to form an ingot. The enclosure is preferably constructed in at least two parts to enable easy transport of the apparatus from one nuclear site to another. 8 figs.

Newman, D.F.; Ross, W.A.

1990-04-24T23:59:59.000Z

30

Radioactive waste material melter apparatus  

DOE Patents (OSTI)

An apparatus for preparing metallic radioactive waste material for storage is disclosed. The radioactive waste material is placed in a radiation shielded enclosure. The waste material is then melted with a plasma torch and cast into a plurality of successive horizontal layers in a mold to form a radioactive ingot in the shape of a spent nuclear fuel rod storage canister. The apparatus comprises a radiation shielded enclosure having an opening adapted for receiving a conventional transfer cask within which radioactive waste material is transferred to the apparatus. A plasma torch is mounted within the enclosure. A mold is also received within the enclosure for receiving the melted waste material and cooling it to form an ingot. The enclosure is preferably constructed in at least two parts to enable easy transport of the apparatus from one nuclear site to another.

Newman, Darrell F. (Richland, WA); Ross, Wayne A. (Richland, WA)

1990-01-01T23:59:59.000Z

31

Storage depot for radioactive material  

Science Conference Proceedings (OSTI)

Vertical drilling of cylindrical holes in the soil, and the lining of such holes, provides storage vaults called caissons. A guarded depot is provided with a plurality of such caissons covered by shielded closures preventing radiation from penetrating through any linear gap to the atmosphere. The heat generated by the radioactive material is dissipated through the vertical liner of the well into the adjacent soil and thus to the ground surface so that most of the heat from the radioactive material is dissipated into the atmosphere in a manner involving no significant amount of biologically harmful radiation. The passive cooling of the radioactive material without reliance upon pumps, personnel, or other factor which might fail, constitutes one of the most advantageous features of this system. Moreover this system is resistant to damage from tornadoes or earthquakes. Hermetically sealed containers of radioactive material may be positioned in the caissons. Loading vehicles can travel throughout the depot to permit great flexibility of loading and unloading radioactive materials. Radioactive material can be shifted to a more closely spaced caisson after ageing sufficiently to generate much less heat. The quantity of material stored in a caisson is restricted by the average capacity for heat dissipation of the soil adjacent such caisson.

Szulinski, Milton J. (Richland, WA)

1983-01-01T23:59:59.000Z

32

Storage depot for radioactive material  

SciTech Connect

Vertical drilling of cylindrical holes in the soil, and the lining of such holes, provides storage vaults called caissons. A guarded depot is provided with a plurality of such caissons covered by shielded closures preventing radiation from penetrating through any linear gap to the atmosphere. The heat generated by the radioactive material is dissipated through the vertical liner of the well into the adjacent soil and thus to the ground surface so that most of the heat from the radioactive material is dissipated into the atmosphere in a manner involving no significant amount of biologically harmful radiation. The passive cooling of the radioactive material without reliance upon pumps, personnel, or other factor which might fail, constitutes one of the most advantageous features of this system. Moreover this system is resistant to damage from tornadoes or earthquakes. Hermetically sealed containers of radioactive material may be positioned in the caissons. Loading vehicles can travel throughout the depot to permit great flexibility of loading and unloading radioactive materials. Radioactive material can be shifted to a more closely spaced caisson after ageing sufficiently to generate much less heat. The quantity of material stored in a caisson is restricted by the average capacity for heat dissipation of the soil adjacent such caisson.

Szulinski, M.J.

1983-10-18T23:59:59.000Z

33

Radioactive waste material disposal  

DOE Patents (OSTI)

The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide. 3 figs.

Forsberg, C.W.; Beahm, E.C.; Parker, G.W.

1995-10-24T23:59:59.000Z

34

Radioactive waste material disposal  

DOE Patents (OSTI)

The invention is a process for direct conversion of solid radioactive waste, particularly spent nuclear fuel and its cladding, if any, into a solidified waste glass. A sacrificial metal oxide, dissolved in a glass bath, is used to oxidize elemental metal and any carbon values present in the waste as they are fed to the bath. Two different modes of operation are possible, depending on the sacrificial metal oxide employed. In the first mode, a regenerable sacrificial oxide, e.g., PbO, is employed, while the second mode features use of disposable oxides such as ferric oxide.

Forsberg, Charles W. (155 Newport Dr., Oak Ridge, TN 37830); Beahm, Edward C. (106 Cooper Cir., Oak Ridge, TN 37830); Parker, George W. (321 Dominion Cir., Knoxville, TN 37922)

1995-01-01T23:59:59.000Z

35

Emergency Responder Radioactive Material Quick Reference Sheet...  

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

Transportation Emergency Preparedness Program (TEPP) Emergency Responder Radioactive Material Quick Reference Sheet...

36

Storage containers for radioactive material  

DOE Patents (OSTI)

A radioactive material storage system is claimed for use in the laboratory having a flat base plate with a groove in one surface thereof and a hollow pedestal extending perpendicularly away from the other surface thereof, a sealing gasket in the groove, a cover having a filter therein and an outwardly extending flange which fits over the plate, the groove and the gasket, and a clamp for maintaining the cover and the plate sealed together. The plate and the cover and the clamp cooperate to provide a storage area for radioactive material readily accessible for use or inventory. Wall mounts are provided to prevent accidental formation of critical masses during storage.

Groh, E.F.; Cassidy, D.A.; Dates, L.R.

1980-07-31T23:59:59.000Z

37

Fissile material disposition program: Screening of alternate immobilization candidates for disposition of surplus fissile materials  

Science Conference Proceedings (OSTI)

With the end of the Cold War, the world faces for the first time the need to dismantle vast numbers of ``excess`` nuclear weapons and dispose of the fissile materials they contain, together with fissile residues in the weapons production complex left over from the production of these weapons. If recently agreed US and Russian reductions are fully implemented, tens of thousands of nuclear weapons, containing a hundred tons or more of plutonium and hundreds of tonnes* of highly enriched uranium (HEU), will no longer be needed worldwide for military purposes. These two materials are the essential ingredients of nuclear weapons, and limits on access to them are the primary technical barrier to prospective proliferants who might desire to acquire a nuclear weapons capability. Theoretically, several kilograms of plutonium, or several times that amount of HEU, is sufficient to make a nuclear explosive device. Therefore, these materials will continue to be a potential threat to humanity for as long as they exist.

Gray, L.W.

1996-01-08T23:59:59.000Z

38

EIS-0229: Storage and Disposition of Weapons-Usable Fissile Materials |  

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

29: Storage and Disposition of Weapons-Usable Fissile 29: Storage and Disposition of Weapons-Usable Fissile Materials EIS-0229: Storage and Disposition of Weapons-Usable Fissile Materials Summary The EIS will evaluate the reasonable alternatives and potential environmental impacts for the proposed siting, construction, and operation of three types of facilities for plutonium disposition. Public Comment Opportunities None available at this time. Documents Available For Download September 5, 2007 EIS-0229: Supplement Analysis (September 2007) Storage of Surplus Plutonium Materials at the Savannah River Site November 14, 2003 EIS-0229: Record of Decision (November 2003) Storage and Disposition of Weapons-Usable Fissile Materials November 7, 2003 EIS-0229-SA-03: Supplement Analysis Fabrication of Mixed Oxide Fuel Lead Assemblies in Europe

39

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...

40

SELECTION OF SURPLUS PLUTONIUM MATERIALS FOR DISPOSITION TO WIPP  

SciTech Connect

The U.S. Department of Energy (DOE) is preparing a Surplus Plutonium Disposition (SPD) Supplemental Environmental Impact Statement (SEIS). Included in the evaluation are up to 6 metric tons (MT) of plutonium in the form of impure oxides and metals for which a disposition plan has not been decided, among options that include preparation as feed for the Mixed Oxide Fuel Fabrication Facility; disposing to high-level waste through the Savannah River Site (SRS) HB Line and H Canyon; can-in-canister disposal using the SRS Defense Waste Processing Facility; and preparation for disposal at the Waste Isolation Pilot Plant (WIPP). DOE and SRS have identified at least 0.5 MT of plutonium that, because of high levels of chemical and isotopic impurities, is impractical for disposition by methods other than the WIPP pathway. Characteristics of these items and the disposition strategy are discussed.

Allender, J.; Mcclard, J.; Christopher, J.

2012-06-08T23:59:59.000Z

Note: This page contains sample records for the topic "disposition radioactive materials" 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

EPRI Report on Solid Material Disposition: Evaluation to Assess Industry Impact  

Science Conference Proceedings (OSTI)

In March 2005, the NRC staff requested Commission approval for publication of a proposed rule in the Federal Register to amend 10CFR Part 20 to include criteria for controlling the disposition of solid materials. This report provides an initial analysis of whether or not methods of solid material assessment, currently practiced at nuclear power facilities, would be sufficient to meet the disposition limits in the proposed rule.

2005-12-01T23:59:59.000Z

42

Transporting & Shipping Hazardous Materials at LBNL: Radioactive Materials  

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

Radioactive Materials Radioactive Materials Refer to transportation guidelines in the applicable Radioactive Work Authorization (RWA). Contact the Radiation Protection Group (x7652) if transportation assistance is needed or if radioactive materials need to be shipped. Refer to RPG's Zone sheet to identifying the RCT or HP for your building: https://ehswprod.lbl.gov/rpg/who_to_call.shtml Need radioactive material shipped from LBNL? Please complete the request for shipment form online, print, sign, and forward to your building assigned RPG support person: RPG Transportation - Request for Shipment Form: http://www.lbl.gov/ehs/rpg/assets/docs/Transportation4.pdf Receiving radioactive material at LBNL? If receiving radioactive material at LBNL; radioactive material should be sent to the following address:

43

Diverter assembly for radioactive material  

DOE Patents (OSTI)

A diverter assembly for diverting a pneumatically conveyed holder for a radioactive material between a central conveying tube and one of a plurality of radially offset conveying tubes includes an airtight container. A diverter tube having an offset end is suitably mounted in the container for rotation. A rotary seal seals one end of the diverter tube during and after rotation of the diverter tube while a spring biased seal seals the other end of the diverter tube which moves between various offset conveying tubes. An indexing device rotatably indexes the diverter tube and this indexing device is driven by a suitable drive. The indexing mechanism is preferably a geneva-type mechanism to provide a locking of the diverter tube in place. 3 figs.

Andrews, K.M.; Starenchak, R.W.

1988-04-11T23:59:59.000Z

44

DOE - Safety of Radioactive Material Transportation  

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

of radioactive material are determined by the Nuclear Regulatory Commission (NRC), Department of Transportation (DOT), Department of Energy (DOE), and U.S. Postal...

45

Radiation Machines and Radioactive Materials (Iowa)  

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

These chapters describe general provisions and regulatory requirements; registration, licensure, and transportation of radioactive materials; and exposure standards for radiation protection.

46

Radiation Sources and Radioactive Materials (Connecticut)  

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

These regulations apply to persons who receive, transfer, possess, manufacture, use, store, handle, transport or dispose of radioactive materials and/or sources of ionizing radiation. Some...

47

Radioactive Materials Transportation and Incident Response  

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

FEMA 358, 0510 Q A RADIOACTIVE MATERIALS Transportation Emergency Preparedness Program U.S. Department of Energy TRANSPORTATION AND INCIDENT RESPONSE Q&A About Incident Response Q...

48

Scrap metal management issues associated with naturally occurring radioactive material  

Science Conference Proceedings (OSTI)

Certain industrial processes sometimes generate waste by-products that contain naturally occurring radioactive material (NORM) at elevated concentrations. Some industries, including the water treatment, geothermal energy, and petroleum industries, generate scrap metal that may be contaminated with NORM wastes. Of these three industries, the petroleum industry probably generates the largest quantity of NORM-contaminated equipment, conservatively estimated at 170,000 tons per year. Equipment may become contaminated when NORM-containing scale or sludge accumulates inside water-handling equipment. The primary radionuclides of concern in these NORM wastes are radium-226 and radium-228. NORM-contaminated equipment generated by the petroleum industry currently is managed several ways. Some equipment is routinely decontaminated for reuse; other equipment becomes scrap metal and may be disposed of by burial at a licensed landfill, encapsulation inside the wellbore of an abandoned well, or shipment overseas for smelting. In view of the increased regulatory activities addressing NORM, the economic burden of managing NORM-contaminated wastes, including radioactive scrap metal, is likely to continue to grow. Efforts to develop a cost-effective strategy for managing radioactive scrap metal should focus on identifying the least expensive disposition options that provide adequate protection of human health and the environment. Specifically, efforts should focus on better characterizing the quantity of radioactive scrap available for recycle or reuse, the radioactivity concentration levels, and the potential risks associated with different disposal options.

Smith, K.P.; Blunt, D.L.

1995-08-01T23:59:59.000Z

49

Radioactive Material or Multiple Hazardous Materials Decontamination  

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

The purpose of this procedure is to provide guidance for performing decontamination ofindividuals who have entered a hot zone during transportation incidents involving radioactive.

50

DOE - Safety of Radioactive Material Transportation  

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

SAFE are radioactive material transportations packages? SAFE are radioactive material transportations packages? RAM PACKAGES TESTING & CERTIFICATION REGULATIONS & GUIDANCE SITE MAP This graphic was generated from a computer analysis and shows the results from a regulatory puncture test of a stainless steel packaging dropping 40 inches (10 MPH) onto a 6 inch diameter steel spike. U.S. DOE | Office of Civilian Radioactive Waste Management (OCRWM) Sandia National Laboratories | Nuclear Energy & Fuel Cucle Programs © Sandia Corporation | Site Contact | Sandia Site Map | Privacy and Security An internationally recognized web-site from PATRAM 2001 - the 13th International Symposium on the Packaging and Transportation of Radioactive Material. Recipient of the AOKI AWARD. PATRAM, sponsored by the U.S. Department of Energy in cooperation with the International Atomic Energy Agency brings government and industry leaders together to share information on innovations, developments, and lessons learned about radioactive materials packaging and transportation.

51

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

52

Storage and Disposition of Weapons-Usable Fissile Materials  

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

86 86 Federal Register / Vol. 63, No. 156 / Thursday, August 13, 1998 / Notices 1 SRS has been identified by DOE as the preferred site for the immobilization disposition facility. responsibilities are to (1) evaluate the standards of accreditation applied to applicant foreign medical schools; and (2) determine the comparability of those standards to standards for accreditation applied to United States medical schools. For Further Information Contact: Bonnie LeBold, Executive Director, National Committee on Foreign Medical Education and Accreditation, 7th and D Streets, S.W., Room 3082, ROB #3, Washington, D.C. 20202-7563. Telephone: (202) 260-3636. Beginning September 28, 1998, you may call to obtain the identity of the countries whose standards are to be evaluated during this

53

Using Neutrons to Study Radioactive Materials  

Science Conference Proceedings (OSTI)

Symposium, Applied Neutron Scattering in Engineering and Materials Science Research ... to the unique infrastructure and specialized staff of the Nuclear Laboratory. Shielded cells enable neutron diffraction studies on highly radioactive...

54

Radioactive materials shipping cask anticontamination enclosure  

DOE Patents (OSTI)

An anticontamination device for use in storing shipping casks for radioactive materials comprising (1) a seal plate assembly; (2) a double-layer plastic bag; and (3) a water management system or means for water management.

Belmonte, Mark S. (Irwin, PA); Davis, James H. (Pittsburgh, PA); Williams, David A. (Pittsburgh, PA)

1982-01-01T23:59:59.000Z

55

DOE - Safety of Radioactive Material Transportation  

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

What's their construction? Who uses them? Who makes rules? What are the requirements? Safety Record Radioactive materials are carried by road, rail, water, and air. There are strict regulations that originate from the International Atomic Energy Agency (IAEA) which cover the packaging and transportation of radioactive materials. Road Rail Water Air [Road transport] Click to view picture [Rail transport] Click to view picture [Sea transport] Click to view picture [Air transport] Click to view picture 1998 DOE Radioactive Shipments in the United States Out of the 3 million hazardous material shipments are made each year, DOE accounts for less than 1% of all radioactive materials shipments and 75% of the total curies shipped in the United States Ship 0 Train 308

56

Radioactive Samples / Materials at the APS  

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

Using Radioactive Samples / Materials at the APS Using Radioactive Samples / Materials at the APS The use of radioactive samples requires additional information for review and approval. All proposed experiments involving radioactive samples will be reviewed by the APS Radioactive Sample Safety Review Committee (RSSRC). The review will be on a graded basis. Hence, the experimenters are strongly advised to send in the experiment proposal in detail at least 2 months before the expected scheduled date of the experiment. Previously approved containment, isotopes and weights can be submitted as late as 2 weeks in advance. If your ESAF was submitted less than seven (7) days in advance of its scheduled start date you may be delayed to allow time for a safety review. The following guidelines are to be followed for all experiments with

57

DOE - Safety of Radioactive Material Transportation  

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

What are the requirements? What are the requirements? Safety Record Radioactive material has been shipped in the U. S. for more than 50 years with no occurrences of death or serious injury from exposure of the contents of these shipments. Hazardous Material Shipments for 1 Year Internationally 300 million United States 3 million DOE <1% or 5,000 (out of 3 million) [U.S. DOE NTP, 1999, Transporting Radioactive Materials] All radioactive shipments are regulated by the Department of Transportation (DOT) and the Nuclear Regulatory Commission (NRC). Since transport accidents cannot be prevented, the regulations are primarily designed to: Insure safety in routine handling situations for minimally hazardous material Insure integrity under all circumstances for highly dangerous materials

58

Radioactivity Standard Reference Material Program  

Science Conference Proceedings (OSTI)

... Summary: The Standard Reference Materials Program of the National Institute of Standards and Technology (NIST) provides science, industry, and ...

2013-03-27T23:59:59.000Z

59

DOE - Safety of Radioactive Material Transportation  

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

What are the requirements? Safety Record The Agencies that Generate Rules that Promulgate the Transport of Radioactive Materials: Regulations to control the transport of radioactive material were initiated about 1935 by the Postal Service. Over the years, the Interstate Commerce Commission (ICC) became involved and in 1948 promulgated regulations as Title 49 of the Code of Federal Regulations. In 1966, DOT received hazardous materials regulatory authority that had been exercised by the ICC, Federal Aviation Administration (FAA) and United States Costal Guard (USCG). Currently, five groups generate rules governing the transport of radioactive material -- the DOT, NRC, USPS, DOE, and various State agencies. Among these, DOT and NRC are the primary agencies issuing regulations based on the model regulations developed by the International Atomic Energy Agency (IAEA).

60

DOE - Safety of Radioactive Material Transportation  

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

When are they used? How are they moved? What's their construction? Who uses them? Who makes rules? What are the requirements? Safety Record A radioactive material (RAM) packaging is a container that is used to safely transport radioactive material from one location to another. In RAM transportation the container alone is called the Packaging. The packaging together with its contents is called the Package. Basic types of radioactive material packagings are: Excepted Packaging Industrial Packaging Type A Packaging Type B Packaging [EXCEPTED] Click to view picture [IP] Click to view picture [TYPE A] Click to view picture [TYPE B] Click to view picture Excepted Packagings are designed to survive normal conditions of transport. Excepted packagings are used for transportation of materials that are either Low Specific Activity (LSA) or Surface Contaminated Objects (SCO) and that are limited quantity shipments, instruments or articles, articles manufactured from natural or depleted uranium or natural thorium; empty packagings are also excepted (49CFR 173.421-428).

Note: This page contains sample records for the topic "disposition radioactive materials" 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

ALTERNATE MATERIALS IN DESIGN OF RADIOACTIVE MATERIAL PACKAGES  

SciTech Connect

This paper presents a summary of design and testing of material and composites for use in radioactive material packages. These materials provide thermal protection and provide structural integrity and energy absorption to the package during normal and hypothetical accident condition events as required by Title 10 Part 71 of the Code of Federal Regulations. Testing of packages comprising these materials is summarized.

Blanton, P.; Eberl, K.

2010-07-09T23:59:59.000Z

62

The environmental assessment of nuclear materials disposition options: A transportation perspective  

SciTech Connect

The US Department of Energy has undertaken a program to evaluate and select options for the long-term storage and disposition of fissile materials declared surplus to defense needs as a result of the end of the Cold War. The transport of surplus fissile material will be an important and highly visible aspect of the environmental impact studies and other planning documents required for implementation of the disposition options. This report defines the roles and requirements for transportation of fissile materials in the program, and discusses an existing methodology for determining the environmental impact in terms of risk. While it will be some time before specific alternatives are chosen that will permit the completion of detailed risk calculations, the analytical models for performing the probabilistic risk assessments already exist with much of the supporting data related to the transportation system. This report summarizes the various types of data required and identifies sources for that data.

Wilson, R.K.; Clauss, D.B.; Moyer, J.W.

1994-12-31T23:59:59.000Z

63

DOE - Safety of Radioactive Material Transportation  

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

Specific Activity Specific Activity Low Specific Activity (LSA) material means Class 7 (radioactive) material with limited specific activity which satisfies the descriptions and limits set forth below. Shielding materials surrounding the LSA material may not be considered in determining the estimated average specific activity of the package contents. LSA material must be in one of three groups: LSA-I (i) Ores containing only naturally occurring radionuclides (e.g., uranium, thorium) and uranium or thorium concentrates of such ores; or (ii) Solid unirradiated natural uranium or depleted uranium or natural thorium or their solid or liquid compounds or mixtures; or (iii) Class 7 (radioactive) material, other than fissile material, for which the A2 value is unlimited; or

64

DOE - Safety of Radioactive Material Transportation  

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

Emergency Response Effects of Radiation History Gallery Glossary of Nuclear Terms [Majority from NRC] Contacts Comments & Questions Agencies U. S. Department of Transportation (DOT), U. S. Nuclear Regulatory Commission (NRC) Postal Services (USPS) U. S. Department of Energy (DOE), National Conference of State Legislatures - Environment, Energy and Transportation Program, Hazardous and Radioactive Materials International Atomic Energy Agency (IAEA) U. S. Environmental Protection Agency (EPA) Regulations Code of Federal Regulations: Title 10 - Energy Code of Federal Regulations: Title 10, PART 71 - Packaging and Transportation of Radioactive Material Code of Federal Regulations: Title 49 - Transportation Code of Federal Regulations: Title 49, PART 173 - Shippers - General

65

Interim Report on the Disposition of Solid Material: Comparative Review of Three Published Clearance Guides  

Science Conference Proceedings (OSTI)

As part of the rulemaking process, the U.S. Nuclear Regulatory Commission (NRC) is currently evaluating alternative approaches to control the disposition of solid material at nuclear facilities. The proposed rule would likely incorporate a dose-based criterion. While the NRC has been developing the scope and details of a rule, various national and international organizations have reported dose-based activity concentration levels that utilities may apply to clearance. This document evaluates and discusses...

2004-11-15T23:59:59.000Z

66

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

SciTech Connect

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

Magoulas, V.

2013-06-03T23:59:59.000Z

67

DISCHARGE DEVICE FOR RADIOACTIVE MATERIAL  

DOE Patents (OSTI)

A device is described fur unloading bodies of fissionable material from a neutronic reactor. It is comprised essentially of a wheeled flat car having a receptacle therein containing a liquid coolant fur receiving and cooling the fuel elements as they are discharged from the reactor, and a reciprocating plunger fur supporting the fuel element during discharge thereof prior to its being dropped into the coolant. The flat car is adapted to travel along the face of the reactor adjacent the discharge ends of the coolant tubes.

Ohlinger, L.A.

1958-09-23T23:59:59.000Z

68

Disposition and transportation of surplus radioactive low specific activity nitric acid. Volume 1, Environmental Assessment  

Science Conference Proceedings (OSTI)

DOE is deactivating the PUREX plant at Hanford; this will involve the disposition of about 692,000 liters (183,000 gallons) of surplus nitric acid contaminated with low levels of U and other radionuclides. The nitric acid, designated as low specific activity, is stored in 4 storage tanks at PUREX. Five principal alternatives were evaluated: transfer for reuse (sale to BNF plc), no action, continued storage in Hanford upgraded or new facility, consolidation of DOE surplus acid, and processing the LSA nitric acid as waste. The transfer to BNF plc is the preferred alternative. From the analysis, it is concluded that the proposed disposition and transportation of the acid does not constitute a major federal action significantly affecting the quality of the human environment within the meaning of NEPA; therefore an environmental impact statement is not required.

NONE

1995-05-01T23:59:59.000Z

69

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

70

DOE - Safety of Radioactive Material Transportation  

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

How are they moved? What's their construction? Who uses them? Who makes rules? What are the requirements? Safety Record Packagings are used to safely transport radioactive materials across the United States in over 1.6 million shipments per year. [Weiner et. al., 1991, Risk Analysis, Vol. 11, No. 4, p. 663] Most shipments are destined for hospitals and medical facilities. Other destinations include industrial, research and manufacturing plants, nuclear power plants and national defense facilities. The last comprehensive survey showed that less than 1 percent of these shipments involve high-level radioactive material. [Javitz et. al., 1985, SAND84-7174, Tables 4 and 8] The types of materials transported include: Surface Contaminated Object (SCO) Low Specific Activity (LSA) materials, Low-Level Waste (LLW),

71

Development of an alternate pathway for materials destined for disposition to WIPP  

Science Conference Proceedings (OSTI)

The Los Alamos National Laboratory currently has an inventory of process residues that may be viable candidates for disposition to the Waste Isolation Pilot Project (WIPP) located at Carlsbad, New Mexico. A recent 'Attractiveness Level D' exemption allows for the discard of specified intractable materials regardless of the percent plutonium. However, the limits with respect to drum loadings must be met. Cementation is a key component of the aqueous nitrate flowsheet and serves as a 'bleed-off' stream for impurities separated from the plutonium during processing operations. The main 'feed' to the cementation operations are the 'bottoms' from the evaporation process. In the majority of cases, the cemented bottoms contain less than the allowed amount per drum for WIPP acceptance. This project would expand the route to WIPP for items that have no defined disposition path, are difficult to process, have been through multiple passes, have no current recovery operations available to recover the plutonium and that are amenable to cementation. This initial work will provide the foundation for a full scale disposition pathway of the candidate materials. Once the pathway has been expanded and a cementation matrix developed, routine discard activities will be initiated.

Ayers, Georgette Y [Los Alamos National Laboratory; Mckerley, Bill [Los Alamos National Laboratory; Veazey, Gerald W [Los Alamos National Laboratory; Ricketts, Thomas E [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

72

EMERGENCY RESPONSE TO A TRANSPORTATION ACCIDENT INVOLVING RADIOACTIVE MATERIAL  

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

Emer Emer Emer Emer Emer Emergency Response to a T gency Response to a T gency Response to a T gency Response to a T gency Response to a Transportation ransportation ransportation ransportation ransportation Accident Involving Radioactive Material Accident Involving Radioactive Material Accident Involving Radioactive Material Accident Involving Radioactive Material Accident Involving Radioactive Material DISCLAIMER DISCLAIMER DISCLAIMER DISCLAIMER DISCLAIMER Viewing this video and completing the enclosed printed study material do not by themselves provide sufficient skills to safely engage in or perform duties related to emergency response to a transportation accident involving radioactive material. Meeting that goal is beyond the scope of this video and requires either additional

73

Controlling Beryllium Contaminated Material And Equipment For The Building 9201-5 Legacy Material Disposition Project  

SciTech Connect

This position paper addresses the management of beryllium contamination on legacy waste. The goal of the beryllium management program is to protect human health and the environment by preventing the release of beryllium through controlling surface contamination. Studies have shown by controlling beryllium surface contamination, potential airborne contamination is reduced or eliminated. Although there are areas in Building 9201-5 that are contaminated with radioactive materials and mercury, only beryllium contamination is addressed in this management plan. The overall goal of this initiative is the compliant packaging and disposal of beryllium waste from the 9201-5 Legacy Material Removal (LMR) Project to ensure that beryllium surface contamination and any potential airborne release of beryllium is controlled to levels as low as practicable in accordance with 10 CFR 850.25.

Reynolds, T. D.; Easterling, S. D.

2010-10-01T23:59:59.000Z

74

Radioactive Material Use at the EMSL Radiochemistry Annex  

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

Material Use at the EMSL Radiochemistry Annex Material Use at the EMSL Radiochemistry Annex The EMSL Radiochemistry Annex, located in the 3410 Material Science and Technology Building, is authorized to work with small to moderate amounts of radioactive material. In order to work within 3410 facility radiological limits, potential users must provide detailed information about the type and quantity of radioactive material, the form and packaging of the material and the type of work that will be performed at the EMSL Radiochemistry Annex. Radioactive material includes both purchased radioactive material and samples that contain concentrations of radioactive material in excess of normal background levels. Please realize that some samples that may not be considered to be radioactive material at your institution will be managed as radioactive material at

75

Radioactive Materials Transportation and Incident Response  

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

FEMA 358, 05/10 FEMA 358, 05/10 Q A RADIOACTIVE MATERIALS Transportation Emergency Preparedness Program U.S. Department of Energy TRANSPORTATION AND INCIDENT RESPONSE Q&A About Incident Response Q Q Law Enforcement ____________________________________ Fire ___________________________________________ Medical ____________________________________________ State Radiological Assistance ___________________________ Local Government Official ______________________________ Local Emergency Management Agency ___________________ State Emergency Management Agency ___________________ HAZMAT Team ______________________________________ Water Pollution Control ________________________________ CHEMTEL (Toll-free US & Canada) 1-800-255-3924 _________ CHEMTREC (Toll-free US & Canada) 1-800-424-9300 _______

76

RadTrac: Portable and Compact Tracking Radioactive Materials  

Hot cell exits where radioactive materials are used, or at nonproliferation sites Defense companies and airport security equipment manufacturers

77

Corrosion resistant storage container for radioactive material  

DOE Patents (OSTI)

A corrosion resistant long-term storage container for isolating high-level radioactive waste material in a repository is claimed. The container is formed of a plurality of sealed corrosion resistant canisters of different relative sizes, with the smaller canisters housed within the larger canisters, and with spacer means disposed between juxtaposed pairs of canisters to maintain a predetermined spacing between each of the canisters. The combination of the plural surfaces of the canisters and the associated spacer means is effective to make the container capable of resisting corrosion, and thereby of preventing waste material from leaking from the innermost canister into the ambient atmosphere.

Schweitzer, D.G.; Davis, M.S.

1984-08-30T23:59:59.000Z

78

Hanford Site radioactive hazardous materials packaging directory  

SciTech Connect

The Hanford Site Radioactive Hazardous Materials Packaging Directory (RHMPD) provides information concerning packagings owned or routinely leased by Westinghouse Hanford Company (WHC) for offsite shipments or onsite transfers of hazardous materials. Specific information is provided for selected packagings including the following: general description; approval documents/specifications (Certificates of Compliance and Safety Analysis Reports for Packaging); technical information (drawing numbers and dimensions); approved contents; areas of operation; and general information. Packaging Operations & Development (PO&D) maintains the RHMPD and may be contacted for additional information or assistance in obtaining referenced documentation or assistance concerning packaging selection, availability, and usage.

McCarthy, T.L.

1995-12-01T23:59:59.000Z

79

DOE - Safety of Radioactive Material Transportation  

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

Sources of Radiation Biological Responses Other Effects History Gallery Glossary of Nuclear Terms [Majority from NRC] Contacts Comments & Questions Radiation is all around us, occurring naturally in the environment. We are always exposed to radiation from: radon in the air uranium, radium and thorium in the earth cosmic rays from outer space and the sun radioactive potassium in our food and water naturally occuring radioactive material within our own bodies. This is commonly called "naturally-occurring background radiation." TYPES OF IONIZING RADIATION Alpha Alpha particles can be shielded by a sheet of paper or by human skin. If alpha emitters are inhaled, ingested, or enter the body through a cut, they can cause cancer. Beta Beta radiation can be stopped by a shield like aluminum foil or wood. If beta emitters are inhaled, ingested, or enter the body through a cut, they can cause cancer.

80

Midwestern Radioactive Materials Transportation Committee Agenda  

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

Council of State Governments Council of State Governments Midwestern Radioactive Materials Transportation Committee May 15, 2012 Knoxville, Tennessee Revised Agenda 9 - 9:45 am Welcome, Introductions, and Committee Reports Report from co-chairs Tim Runyon (Illinois) Project update Lisa Janairo, CSG Midwest Work group reports Integrated Spent Fuel Management Work Group Teri Engelhart (Wisconsin) NTSF-related reports Planning Committee Tim Runyon (Illinois) Communications Ad Hoc Working Group Jane Beetem (Missouri) WIPP Security Communications Protocol Major Lance Evans (Iowa) Ad Hoc Working Group Information and Communications Work Group Lisa Janairo 9:45 - 10:45 am Committee Discussion Blue Ribbon Commission final report: state reactions, next steps

Note: This page contains sample records for the topic "disposition radioactive materials" 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

RECLAMATION OF RADIOACTIVE MATERIAL PACKAGING COMPONENTS  

SciTech Connect

Radioactive material packages are withdrawn from use for various reasons; loss of mission, decertification, damage, replacement, etc. While the packages themselves may be decertified, various components may still be able to perform to their required standards and find useful service. The Packaging Technology and Pressurized Systems group of the Savannah River National Laboratory has been reducing the cost of producing new Type B Packagings by reclaiming, refurbishing, and returning to service the containment vessels from older decertified packagings. The program and its benefits are presented.

Abramczyk, G.; Nathan, S.; Loftin, B.; Bellamy, S.

2011-06-06T23:59:59.000Z

82

Materials Sustainability: Digital Resource Center - Radioactivity in ...  

Science Conference Proceedings (OSTI)

Jun 26, 2008 ... This video introduces terms and concepts associated with radioactivity and shows how to identify radioactive substances that might enter a...

83

Experiment Hazard Class 8.1 - Radioactive Materials/Samples  

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

1 - Radioactive Materials 1 - Radioactive Materials Applicability This hazard classification applies to all experiments involving radioactive materials as samples. The requirements of this hazard class also apply to sealed radioactive sources that are used as a sample (i.e. a target for x-ray radiation). Other hazard classifications and their associated hazard controls may also apply to experiments in this hazard class. The current requirements can be found in the APS Policy for Conducting Radioactive Sample Experiments in APS Experiment Enclosures. NOTE: The APS must be notified of shipment of any radioactive materials to the site well in advance of the proposed experiment. All radioactive materials must arrive through Argonne Receiving in Building 46 and the Argonne Materials Control & Accountability group (MC&A). Please contact

84

Radiation Awareness TrainingRadiation Awareness Training Radioactive Material &Radioactive Material &  

E-Print Network (OSTI)

;Regulatory Agencies · Radioactive Materials ­ Broad Scope License ­ Issued by GA Department of Natural Resources · X-Ray Machines ­ Units registered with the GA Department of Human Resources ­ They regulate x) · Sealed sources ­ Nickel-63 (Gas chromatograph) ­ Cesium-137 (Liquid Scintillation Counter) ­ Neutron

Löffler, Frank E.

85

Introduction to naturally occurring radioactive material  

SciTech Connect

Naturally occurring radioactive material (NORM) is everywhere; we are exposed to it every day. It is found in our bodies, the food we eat, the places where we live and work, and in products we use. We are also bathed in a sea of natural radiation coming from the sun and deep space. Living systems have adapted to these levels of radiation and radioactivity. But some industrial practices involving natural resources concentrate these radionuclides to a degree that they may pose risk to humans and the environment if they are not controlled. Other activities, such as flying at high altitudes, expose us to elevated levels of NORM. This session will concentrate on diffuse sources of technologically-enhanced (TE) NORM, which are generally large-volume, low-activity waste streams produced by industries such as mineral mining, ore benefication, production of phosphate Fertilizers, water treatment and purification, and oil and gas production. The majority of radionuclides in TENORM are found in the uranium and thorium decay chains. Radium and its subsequent decay products (radon) are the principal radionuclides used in characterizing the redistribution of TENORM in the environment by human activity. We will briefly review other radionuclides occurring in nature (potassium and rubidium) that contribute primarily to background doses. TENORM is found in many waste streams; for example, scrap metal, sludges, slags, fluids, and is being discovered in industries traditionally not thought of as affected by radionuclide contamination. Not only the forms and volumes, but the levels of radioactivity in TENORM vary. Current discussions about the validity of the linear no dose threshold theory are central to the TENORM issue. TENORM is not regulated by the Atomic Energy Act or other Federal regulations. Control and regulation of TENORM is not consistent from industry to industry nor from state to state. Proposed regulations are moving from concentration-based standards to dose-based standards. So when is TENORM a problem? Where is it a problem? That depends on when, where, and whom you talk to! We will start by reviewing background radioactivity, then we will proceed to the geology, mobility, and variability of these radionuclides. We will then review some of the industrial sectors affected by TENORM, followed by a brief discussion on regulatory aspects of the issue.

Egidi, P.

1997-08-01T23:59:59.000Z

86

DOE - Safety of Radioactive Material Transportation  

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

What are full-scale tests? What are scale-model tests? What is computer analysis? What are examples of severe testing? How do the certification tests compare to real-life accidents? Demonstrating target hardness. A packaging is certified when it can survive a sequence of impact, crush, puncture, fire, and immersion tests designed to replicate transport accident conditions. Type B Packages must meet the testing requirements of: Compliance Testing, as defined in 10 CFR Part 71.85 and 10 CFR Part 71.87 Normal Conditions of Transport, Ten tests as defined in 10 CFR Part 71.71 Hypothetical Accident Conditions, Six tests as defined in 10 CFR Part 71.73 The ability of radioactive material packages to withstand testing environments can be demonstrated by full-scale testing, scale-model

87

DOE - Safety of Radioactive Material Transportation  

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

Other Effects History Gallery Glossary of Nuclear Terms [Majority from NRC] Contacts Comments & Questions Dose Rate Calculator Click to use calculator. This tool calculates a dose rate (DR) at 2 meters (about 6 ft) from the surface of a package containing radioactive material IF you know the dose rate at 1 meter (about 3 ft). It will also calculate the reverse; DR at 1 meter if you know the DR at 2 meters. These two distances are used by the Nuclear Regulatory Commission to define acceptable dose rates for packages. Dose (Rad) Biological Effect < 5 rad No immediate observable effects 5 - 50 rad Slight blood changes may be detected by medical evaluation 50 - 150 rad Slight blood changes will be noted and likely symptoms of nausea, fatigue, vomiting, etc.

88

RADIOACTIVE MATERIAL PACKAGING TORQUE REQUIREMENTS COMPLIANCE  

Science Conference Proceedings (OSTI)

Shipping containers used to transport radioactive material (RAM) in commerce employ a variety of closure mechanisms. Often, these closure mechanisms require a specific amount of torque be applied to a bolt, nut or other threaded fastener. It is important that the required preload is achieved so that the package testing and analysis is not invalidated for the purpose of protecting the public. Torque compliance is a means of ensuring closure preload, is a major factor in accomplishing the package functions of confinement/containment, sub-criticality, and shielding. This paper will address the importance of applying proper torque to package closures, discuss torque value nomenclature, and present one methodology to ensure torque compliance is achieved.

Watkins, R.; Leduc, D.

2011-03-24T23:59:59.000Z

89

DECONTAMINATION DRESSDOWN AT A TRANSPORTATION ACCIDENT INVOLVING RADIOACTIVE MATERIAL  

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

Video User' s Guide Video User' s Guide DECONTAMINATION DRESSDOWN AT A TRANSPORTATION ACCIDENT INVOLVING RADIOACTIVE MATERIAL DISCLAIMER Viewing this video and completing the enclosed printed study material do not by themselves provide sufficient skills to safely engage in or perform duties related to emergency response to a transportation accident involving radioactive material. Meeting that goal is beyond

90

Sandia technology used to remove radioactive material at Fukushima...  

National Nuclear Security Administration (NNSA)

technology used to remove radioactive material at Fukushima | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the...

91

Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM  

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

Integrated Facilities Disposition Project Integrated Facilities Disposition Project Technical Assistance Page 1 of 2 Oak Ridge National Laboratory Y-12 National Security Complex Tennessee Tennessee Assessment of the Integrated Facility Disposition Project at ORNL & Y-12 for Transfer of Facilities & Materials to EM Challenge In December 2007, the Assistant Secretary for Environmental Management (EM-1) invited the DOE Program Secretarial Offices (PSOs) of Nuclear Energy (NE), Science (SC), and the National Nuclear Security Administration (NNSA) to propose facilities and legacy waste for transfer to Environmental Management (EM) for final disposition or deactivation and decommissioning (D&D). In parallel with the EM-1 initiative, the Oak Ridge Reservation was conducting a Critical

92

Radioactive Materials at SSRL | Stanford Synchrotron Radiation Lightsource  

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

Radioactive Materials at SSRL Radioactive Materials at SSRL Contact Information SSRL Safety Officer (650) 926-3861 SSRL Radiation Protection Group (650) 926-4299 SSRLRadMat@SLAC.STANFORD.EDU Throughout the course of an SSRL Experimental Run, there are requests from users to transport and use small amounts of radioactive material in their experiments, either as stand alone samples or in a matrix of other materials. There is no minimum quantity for declaring the use of radioactive samples at SSRL. The purpose of this procedure is to enable Users, SSRL and SLAC staff to know what radiological controls will be implemented for these materials, based on the isotope, its toxicity risk and radiological controls. Radioactive materials at SSRL are classified into 4 classification Groups based on the radiotoxicity tables, see below.

93

Evaluation of options for disposition of dispersible material in B-Cell  

SciTech Connect

The radioactive contaminants in the dispersible material in B-cell of the 324 Building Radiochemical Energy (RE) hot-cell complex at the Hanford Site in southeastern Washington exceed the allowable level. In 1986, there was a spill of 1.3 million curies of concentrated cesium and strontium in B-cell. Cleanup is required, and candidate technologies for cleaning up or otherwise addressing problems associated with the dispersible material are being evaluated by Pacific Northwest Laboratory (PNL). The RE hot-cell complex in 324 Building was constructed in the late 1950s. From the early 1960s until today the complex has been the site of numerous research, development, and demonstration programs using radioactive and hazardous materials. In mid-FY 1988, a program to clean B-cell was initiated. At present, dispersible material has been collected from 45% of the cell floor area, and 64% of the equipment and support racks have been removed from the cell. The evaluation of decontamination procedures are described.

Tokarz, R.D.; Defferding, L.J.; Adickes, M.D.; Keene, K.E.; Pilger, J.P.; Alzheimer, J.M. [Pacific Northwest Lab., Richland, WA (United States); Paxton, M.M. [Westinghouse Hanford Co., Richland, WA (United States)

1993-10-01T23:59:59.000Z

94

DOE/EA-1651: Final Environmental Assessment for U-233 Material Downblending and Disposition Project at the Oak Ridge National Laboratory Oak Ridge, Tennessee (January 2010)  

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

51 51 Final Environmental Assessment for U-233 Material Downblending and Disposition Project at the Oak Ridge National Laboratory Oak Ridge, Tennessee U. S. Department of Energy Oak Ridge Office Oak Ridge, Tennessee January 2010 FINDING OF NO SIGNIFICANT IMPACT URANIUM-233 MATERIAL DOWNBLENDING AND DISPOSITION PROJECT AT THE OAK RIDGE NATIONAL LABORATORY, OAK RIDGE, TENNESSEE AGENCY: U.S. Department of Energy (DOE) ACTION: Finding of No Significant Impact (FONSI) SUMMARY: DOE has completed the Final Environmental Assessment for U-233 Material Downblending and Disposition Project at the Oak Ridge National Laboratory [DOE/EA-1651]. This environmental assessment (EA) evaluates the impacts of planned activities to modify selected

95

CLOSURE WELDING RADIOACTIVE MATERIALS CONTAINERS AT THE DEPARTMENT OF ENERGY (DOE) HANFORD SITE  

SciTech Connect

The Department of Energy's (DOE) responsibility for the disposition of radioactive materials has given rise to several unique welding applications. Many of these materials require packaging into containers for either Interim or long-term storage. It is not uncommon that final container fabrication, i.e., closure welding, is performed with these materials already placed into the container. Closure welding is typically performed remote to the container, and routine post-weld testing and nondestructive examination (NDE) are often times not feasible. Fluor Hanford has packaged many such materials in recent years as park of the Site's cleanup mission. In lieu of post-weld testing and NDE, the Fluor-Hanford approach has been to establish weld quality through ''upfront'' development and qualification of welding parameters, and then ensure parameter compliance during welding. This approach requires a rigor not usually afforded to typical welding development activities, and may involve statistical analysis and extensive testing, including burst, drop, sensitive leak testing, etc. This paper provides an instructive review of the development and qualification activities associated with the closure of radioactive materials containers, including a brief report on activities for closure welding research reactor, spent nuclear fuel (SNF) overpacks at the Hanford Site.

CANNELL, G.R.

2006-09-01T23:59:59.000Z

96

Safety and Security Technologies for Radioactive Material Shipments  

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

and Security Technologies for and Security Technologies for Radioactive Material Shipments Safety & Security Technologies Study Started in 2005 with OCRWM Funding. OCRWM funding ended in 2009. EM gave CVSA funding to finish the report. CVSA Ad Hoc RAM/Security/ITS Committee Examined current and emerging technologies for safety and security of radioactive material shipments Site visits Product reviews HMCRP HM-04 report on emerging technologies Safety & Security Technologies Study Completed several site visits to look at current technologies being used. Technologies were broken down into five categories. 1. Inspection Technologies 2. Security Technologies 3. Radioactive Material Dose Rate Measurement and

97

Naturally Occurring Radioactive Materials in Cargo at US Borders  

Science Conference Proceedings (OSTI)

In the U.S. and other countries, large numbers of vehicles pass through border crossings each day. The illicit movement of radioactive sources is a concern that has resulted in the installation of radiation detection and identification instruments at border crossing points. This activity is judged to be necessary because of the possibility of an act of terrorism involving a radioactive source that may include any number of dangerous radionuclides. The problem of detecting, identifying, and interdicting illicit radioactive sources is complicated by the fact that many materials present in cargo are somewhat radioactive. Some cargo contains naturally occurring radioactive material or technologically-enhanced naturally occurring radioactive material that may trigger radiation portal monitor alarms. Man-made radioactive sources, especially medical isotopes, are also frequently observed and produce alarms. Such nuisance alarms can be an operational limiting factor for screening of cargo at border crossings. Information about the nature of the radioactive materials in cargo that can interfere with the detection of radionuclides of concern is necessary. This paper provides such information for North American cargo, but the information may also be of use to border control officials in other countries. (PIET-43741-TM-361)

Kouzes, Richard T.; Ely, James H.; Evans, John C.; Hensley, Walter K.; Lepel, Elwood A.; McDonald, Joseph C.; Schweppe, John E.; Siciliano, Edward R.; Strom, Daniel J.; Woodring, Mitchell L.

2006-01-01T23:59:59.000Z

98

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)

99

Sandia technology used to remove radioactive material at Fukushima |  

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

technology used to remove radioactive material at Fukushima | technology used to remove radioactive material at Fukushima | 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 > Sandia technology used to remove radioactive material ... Sandia technology used to remove radioactive material at Fukushima Posted By Office of Public Affairs

100

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)

Note: This page contains sample records for the topic "disposition radioactive materials" 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

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),

102

Radioactive-materials shipping-cask anticontamination enclosure  

DOE Patents (OSTI)

An anticontamination device for use in storing shipping casks for radioactive materials comprises (1) a seal plate assembly; (2) a double-layer plastic bag; and (3) a water management system or means for water management.

Belmonte, M.S.; Davis, J.H.; Williams, D.A.

1981-08-18T23:59:59.000Z

103

Safety philosophy in the transportation of radioactive material  

SciTech Connect

From Winter meeting of American Society of Mechanical Engineers; Detroit, Michigan, USA (11 Nov 1973). The radiological'' and common cause risks'' involved in transporting radioactive materials are briefly discussed. (TFD)

Langhaar, J.W.

1974-04-30T23:59:59.000Z

104

NNSA Removes High-Activity Radioactive Materials from Boston | National  

National Nuclear Security Administration (NNSA)

Removes High-Activity Radioactive Materials from Boston | National Removes High-Activity Radioactive Materials from Boston | 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 > NNSA Removes High-Activity Radioactive Materials from Boston Press Release NNSA Removes High-Activity Radioactive Materials from Boston Nov 22, 2013

105

Nonproliferation and arms control assessment of weapons-usable fissile material storage and excess plutonium disposition alternatives  

SciTech Connect

This report has been prepared by the Department of Energy`s Office of Arms Control and Nonproliferation (DOE-NN) with support from the Office of Fissile Materials Disposition (DOE-MD). Its purpose is to analyze the nonproliferation and arms reduction implications of the alternatives for storage of plutonium and HEU, and disposition of excess plutonium, to aid policymakers and the public in making final decisions. While this assessment describes the benefits and risks associated with each option, it does not attempt to rank order the options or choose which ones are best. It does, however, identify steps which could maximize the benefits and mitigate any vulnerabilities of the various alternatives under consideration.

1997-01-01T23:59:59.000Z

106

Summary report of the screening process to determine reasonable alternatives for long-term storage and disposition of weapons-usable fissile materials  

SciTech Connect

Significant quantities of weapons-usable fissile materials (primarily plutonium and highly enriched uranium) have become surplus to national defense needs both in the US and Russia. These stocks of fissile materials pose significant dangers to national and international security. The dangers exist not only in the potential proliferation of nuclear weapons but also in the potential for environmental, safety and health consequences if surplus fissile materials are not properly managed. As announced in the Notice of Intent (NOI) to prepare a Programmatic Environmental Impact Statement (PEIS), the Department of Energy is currently conducting an evaluation process for disposition of surplus weapons-usable fissile materials determined surplus to National Security needs, and long-term storage of national security and programmatic inventories, and surplus weapons-usable fissile materials that are not able to go directly from interim storage to disposition. An extensive set of long-term storage and disposition options was compiled. Five broad long-term storage options were identified; thirty-seven options were considered for plutonium disposition; nine options were considered for HEU disposition; and eight options were identified for Uranium-233 disposition. Section 2 discusses the criteria used in the screening process. Section 3 describes the options considered, and Section 4 provides a detailed summary discussions of the screening results.

NONE

1995-03-29T23:59:59.000Z

107

Los Alamos National Laboratory summary plan to fabricate mixed oxide lead assemblies for the fissile material disposition program  

Science Conference Proceedings (OSTI)

This report summarizes an approach for using existing Los Alamos National Laboratory (Laboratory) mixed oxide (MOX) fuel-fabrication and plutonium processing capabilities to expedite and assure progress in the MOX/Reactor Plutonium Disposition Program. Lead Assembly MOX fabrication is required to provide prototypic fuel for testing in support of fuel qualification and licensing requirements. It is also required to provide a bridge for the full utilization of the European fabrication experience. In part, this bridge helps establish, for the first time since the early 1980s, a US experience base for meeting the safety, licensing, safeguards, security, and materials control and accountability requirements of the Department of Energy and Nuclear Regulatory Commission. In addition, a link is needed between the current research and development program and the production of disposition mission fuel. This link would also help provide a knowledge base for US regulators. Early MOX fabrication and irradiation testing in commercial nuclear reactors would provide a positive demonstration to Russia (and to potential vendors, designers, fabricators, and utilities) that the US has serious intent to proceed with plutonium disposition. This report summarizes an approach to fabricating lead assembly MOX fuel using the existing MOX fuel-fabrication infrastructure at the Laboratory.

Buksa, J.J.; Eaton, S.L.; Trellue, H.R.; Chidester, K.; Bowidowicz, M.; Morley, R.A.; Barr, M.

1997-12-01T23:59:59.000Z

108

Used Fuel Disposition Research & Development | Department of Energy  

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

Used Fuel Disposition Used Fuel Disposition Research & Development Used Fuel Disposition Research & Development A typical spent nuclear fuel cask sitting on a railcar. Since the early 1960s, the United States has safely conducted more than 3,000 shipments of used nuclear fuel without any harmful release of radioactive material. A typical spent nuclear fuel cask sitting on a railcar. Since the early 1960s, the United States has safely conducted more than 3,000 shipments of used nuclear fuel without any harmful release of radioactive material. In order to assure the development of a sustainable nuclear fuel cycle for the nation's energy future, to provide a sound technical basis for implementation of a new national policy for managing the back end of the nuclear fuel cycle, and to better understand, assess, and communicate the

109

Development and implementation of automated radioactive materials handling systems  

SciTech Connect

Material handling of radioactive and hazardous materials has forced the need to pursue remotely operated and robotic systems in light of operational safety concerns. Manual maneuvering, repackaging, overpacking and inspecting of containers which store radioactive and hazardous materials is the present mode of operation at the Department of Energy (DOE) Fernald Environmental Management Project (FEMP) in Fernald Ohio. The manual methods are unacceptable in the eyes of concerned site workers and influential community oversight committees. As an example to respond to the FEMP material handling needs, design efforts have been initiated to provide a remotely operated system to repackage thousands of degradated drums containing radioactive Thorium: Later, the repackaged Thorium will be shipped offsite to a predesignated repository again requiring remote operation.

Jacoboski, D.L.

1992-12-01T23:59:59.000Z

110

DOE - Safety of Radioactive Material Transportation  

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

part. It may consist of one or more receptacles, absorbent materials, spacing structures, thermal insulation, radiation shielding, and devices for cooling or absorbing mechanical...

111

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...

112

Waste minimization for commercial radioactive materials users generating low-level radioactive waste. Revision 1  

SciTech Connect

The objective of this document is to provide a resource for all states and compact regions interested in promoting the minimization of low-level radioactive waste (LLW). This project was initiated by the Commonwealth of Massachusetts, and Massachusetts waste streams have been used as examples; however, the methods of analysis presented here are applicable to similar waste streams generated elsewhere. This document is a guide for states/compact regions to use in developing a system to evaluate and prioritize various waste minimization techniques in order to encourage individual radioactive materials users (LLW generators) to consider these techniques in their own independent evaluations. This review discusses the application of specific waste minimization techniques to waste streams characteristic of three categories of radioactive materials users: (1) industrial operations using radioactive materials in the manufacture of commercial products, (2) health care institutions, including hospitals and clinics, and (3) educational and research institutions. Massachusetts waste stream characterization data from key radioactive materials users in each category are used to illustrate the applicability of various minimization techniques. The utility group is not included because extensive information specific to this category of LLW generators is available in the literature.

Fischer, D.K.; Gitt, M.; Williams, G.A.; Branch, S. [EG and G Idaho, Inc., Idaho Falls, ID (United States); Otis, M.D.; McKenzie-Carter, M.A.; Schurman, D.L. [Science Applications International Corp., Idaho Falls, ID (United States)

1991-07-01T23:59:59.000Z

113

Removal of radioactive and other hazardous material from fluid waste  

DOE Patents (OSTI)

Hollow glass microspheres obtained from fly ash (cenospheres) are impregnated with extractants/ion-exchangers and used to remove hazardous material from fluid waste. In a preferred embodiment the microsphere material is loaded with ammonium molybdophosphonate (AMP) and used to remove radioactive ions, such as cesium-137, from acidic liquid wastes. In another preferred embodiment, the microsphere material is loaded with octyl(phenyl)-N-N-diisobutyl-carbamoylmethylphosphine oxide (CMPO) and used to remove americium and plutonium from acidic liquid wastes.

Tranter, Troy J. (Idaho Falls, ID); Knecht, Dieter A. (Idaho Falls, ID); Todd, Terry A. (Aberdeen, ID); Burchfield, Larry A. (W. Richland, WA); Anshits, Alexander G. (Krasnoyarsk, RU); Vereshchagina, Tatiana (Krasnoyarsk, RU); Tretyakov, Alexander A. (Zheleznogorsk, RU); Aloy, Albert S. (St. Petersburg, RU); Sapozhnikova, Natalia V. (St. Petersburg, RU)

2006-10-03T23:59:59.000Z

114

Roadmapping the Resolution of Gas Generation Issues in Packages Containing Radioactive Waste/Materials  

DOE Green Energy (OSTI)

Gas generation issues, particularly hydrogen, have been an area of concern for the transport and storage of radioactive materials and waste in the Department of Energy (DOE) complex. Potentially combustible gases can be generated through a variety of reactions, including chemical reactions and radiolytic decomposition of hydrogen-containing materials. Transportation regulations prohibit shipment of explosives and radioactive materials together. This paper discusses the major gas generation issues within the DOE Complex and the research that has been and is being conducted by the transuranic (TRU) waste, nuclear materials (NM), and spent nuclear fuels (SNF) programs within DOEs Environmental Management (EM) organization to address gas generation concerns. This paper presents a "program level" roadmap that links technology development to program needs and identifies the probability of success in an effort to understand the programmatic risk associated with the issue of gas generation. This "program level" roadmapping involves linking technology development (and deployment) efforts to the programs needs and requirements for dispositioning the material/waste that generates combustible gas through radiolysis and chemical decomposition. The roadmapping effort focused on needed technical & programmatic support to the baselines (and to alternatives to the baselines) where the probability of success is low (i.e., high uncertainty) and the consequences of failure are relatively high (i.e., high programmatic risk). A second purpose for roadmapping was to provide the basis for coordinating sharing of "lessons learned" from research and development (R&D) efforts across DOE programs to increase efficiency and effectiveness in addressing gas generation issues.

Luke, Dale Elden; Rogers, Adam Zachary; Hamp, S.

2001-03-01T23:59:59.000Z

115

DOE - Safety of Radioactive Material Transportation  

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

Who makes rules? What are the requirements? Safety Record USERS OF PACKAGINGS CARRIER PACKAGE TYPE Hospitals and their suppliers common carrier Type A Industrial radiography companies private carrier Type B Soil testing laboratories private carrier Type B Food irradiators contract carrier Type B Medical supply sterilizers contract carrier Type B Academic research institutes common & contract carrier all types Nuclear energy fuel cycle facilities common & contract carrier all types Nuclear weapons complex contract & government carrier all types An agency or company that wants to ship RAM (shipper) often makes arrangements with a common or contract carrier or (where appropriate) a private carrier may transport the material. Packagings may be procured or

116

Radioactive Material Transportation Requirements for the Department of Energy  

Science Conference Proceedings (OSTI)

The Department of Energy (DOE) created the National Transportation Program (NTP) whose goal is to ensure the availability of safe, efficient, and timely transportation of DOE materials. The Integration and Planning Group of the NTP, assisted by Global Technologies Incorporated (GTI), was tasked to identify requirements associated with the transport of DOE Environmental Management (EM) radiological waste/material. A systems engineering approach was used to identify source documents, extract requirements, perform a functional analysis, and set up a transportation requirements management database in RDD-100. Functions and requirements for transporting the following DOE radioactive waste/material are contained in the database: high level radioactive waste (HLW), low-level radioactive waste (LLW), mixed low-level radioactive waste (MLLW), nuclear materials (NM), spent nuclear fuel (SNF), and transuranic waste (TRU waste). The requirements will be used in the development of standard transportation protocols for DOE shipping. The protocols will then be combined into a DOE Transportation Program Management Guide, which will be used to standardize DOE transportation processes.

John, Mark Earl; Fawcett, Ricky Lee; Bolander, Thane Weston

2000-07-01T23:59:59.000Z

117

Self-closing shielded container for use with radioactive materials  

DOE Patents (OSTI)

A container is described for storage of radioactive material comprising a container body and a closure member. The closure member being coupled to the container body to enable the closure body to move automatically from a first position (e.g., closed) to a second position (open). 1 fig.

Smith, J.E.

1984-10-16T23:59:59.000Z

118

Oak Ridge National Laboratory shipping containers for radioactive materials  

Science Conference Proceedings (OSTI)

The types of containers used at ORNL for the transport of radioactive materials are described. Both returnable and non-returnable types are included. Containers for solids, liquids and gases are discussed. Casks for the shipment of uranium, irradiated fuel elements, and non-irradiated fuel elements are also described. Specifications are provided. (DC)

Schaich, R.W.

1980-05-01T23:59:59.000Z

119

Guidelines for the Use of Radioactive Materials in Research  

E-Print Network (OSTI)

Definition of a Radiation Worker 6 Instruction 6 Exposure Monitoring 8 Radiation Exposure Limits 8 Radiation Exposure During Pregnancy 8 Dosimeters 9 Internal Monitoring 10 Radioactive Work Areas 12 Posting Material NCRP National Council on Radiation Protection and Measurements ICRP International Council

120

The radioactive materials packaging handbook: Design, operations, and maintenance  

Science Conference Proceedings (OSTI)

As part of its required activities in 1994, the US Department of Energy (DOE) made over 500,000 shipments. Of these shipments, approximately 4% were hazardous, and of these, slightly over 1% (over 6,400 shipments) were radioactive. Because of DOE`s cleanup activities, the total quantities and percentages of radioactive material (RAM) that must be moved from one site to another is expected to increase in the coming years, and these materials are likely to be different than those shipped in the past. Irradiated fuel will certainly be part of the mix as will RAM samples and waste. However, in many cases these materials will be of different shape and size and require a transport packaging having different shielding, thermal, and criticality avoidance characteristics than are currently available. This Handbook provides guidance on the design, testing, certification, and operation of packages for these materials.

Shappert, L.B.; Bowman, S.M. [Oak Ridge National Lab., TN (United States); Arnold, E.D. [Lockheed Martin Energy Systems, Oak Ridge, TN (United States)] [and others

1998-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "disposition radioactive materials" 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

A manual for implementing residual radioactive material guidelines  

Science Conference Proceedings (OSTI)

This manual presents information for implementing US Department of Energy (DOE) guidelines for residual radioactive material at sites identified by the Formerly Utilized Sites Remedial Action Program (FUSRAP) and the Surplus Facilities Management Program (SFMP). It describes the analysis and models used to derive site-specific guidelines for allowable residual concentrations of radionuclides in soil and the design and use of the RESRAD computer code for calculating guideline values. It also describes procedures for implementing DOE policy for reducing residual radioactivity to levels that are as low as reasonably achievable. 36 refs., 16 figs, 22 tabs.

Gilbert, T.L.; Yu, C.; Yuan, Y.C.; Zielen, A.J.; Jusko, M.J.; Wallo, A. III

1989-06-01T23:59:59.000Z

122

Deep borehole disposition of surplus fissile materials-The site selection process  

Science Conference Proceedings (OSTI)

One option for disposing of excess weapons plutonium is to place it near the base of deep boreholes in stable crystalline rocks. The technology exists to immediately begin the design of this means of disposition and there are many attractive sites available within the conterminous US. The borehole system utilizes mainly natural barriers to preven migration of Pu and U to the Earth`s surface. Careful site selection ensures favorable geologic conditions that provide natural long-lived migration barriers; they include deep, extremely stable rock formations, strongly reducing brines that exhibit increasing salinity with depth, and most importantly, demonstrated isolation or non-communication of deep fluids with the biosphere for millions of years. This isolation is the most important characteristic, with the other conditions mainly being those that will enhance the potential of locating and maintaining the isolated zones. Candidate sites will probably be located on the craton in very old Precambrian crystalline rocks, most likely the center of a granitic pluton. The sites will be located in tectonically stable areas with no recent volcanic or seismic activity, and situated away from tectonic features that might become active in the near geologic future.

Heiken, G.; WoldeGabriel, G.; Morley, R.; Plannerer, H

1996-05-01T23:59:59.000Z

123

RECERTIFICATION OF THE MODEL 9977 RADIOACTIVE MATERIAL PACKAGING  

SciTech Connect

The Model 9977 Packaging was initially issued a Certificate of Compliance (CoC) by the Department of Energys Office of Environmental Management (DOE-EM) for the transportation of radioactive material (RAM) in the Fall of 2007. This first CoC was for a single radioactive material and two packing configurations. In the five years since that time, seven Addendums have been written to the Safety Analysis Report for Packaging (SARP) and five Letter Amendments have been written that have authorized either new RAM contents or packing configurations, or both. This paper will discuss the process of updating the 9977 SARP to include all the contents and configurations, including the addition of a new content, and its submittal for recertification.

Abramczyk, G.; Bellamy, S.; Loftin, B.; Nathan, S.

2013-06-05T23:59:59.000Z

124

Q A RADIOACTIVE MATERIALS Transportation Emergency Preparedness Program  

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

Q A RADIOACTIVE MATERIALS Transportation Emergency Preparedness Program U.S. Department of Energy TRANSPORTATION AND INCIDENT RESPONSE Q&A About Incident Response Q Q Law Enforcement ____________________________________ Fire ___________________________________________ Medical ____________________________________________ State Radiological Assistance ___________________________ Local Government Official ______________________________ Local Emergency Management Agency ___________________ State Emergency Management Agency ___________________ HAZMAT Team ______________________________________ Water Pollution Control ________________________________ CHEMTEL (Toll-free US & Canada) 1-800-255-3924 _________ CHEMTREC (Toll-free US & Canada) 1-800-424-9300 _______

125

Method of encapsulating solid radioactive waste material for storage  

DOE Patents (OSTI)

High-level radioactive wastes are encapsulated in vitreous carbon for long-term storage by mixing the wastes as finely divided solids with a suitable resin, formed into an appropriate shape and cured. The cured resin is carbonized by heating under a vacuum to form vitreous carbon. The vitreous carbon shapes may be further protected for storage by encasement in a canister containing a low melting temperature matrix material such as aluminum to increase impact resistance and improve heat dissipation.

Bunnell, Lee Roy (Kennewick, WA); Bates, J. Lambert (Richland, WA)

1976-01-01T23:59:59.000Z

126

Processing of solid mixed waste containing radioactive and hazardous materials  

DOE Patents (OSTI)

Apparatus for the continuous heating and melting of a solid mixed waste bearing radioactive and hazardous materials to form separate metallic, slag and gaseous phases for producing compact forms of the waste material to facilitate disposal includes a copper split water-cooled (cold) crucible as a reaction vessel for receiving the waste material. The waste material is heated by means of the combination of a plasma torch directed into the open upper portion of the cold crucible and an electromagnetic flux produced by induction coils disposed about the crucible which is transparent to electromagnetic fields. A metallic phase of the waste material is formed in a lower portion of the crucible and is removed in the form of a compact ingot suitable for recycling and further processing. A glass-like, non-metallic slag phase containing radioactive elements is also formed in the crucible and flows out of the open upper portion of the crucible into a slag ingot mold for disposal. The decomposition products of the organic and toxic materials are incinerated and converted to environmentally safe gases in the melter.

Gotovchikov, Vitaly T. (Moscow, RU); Ivanov, Alexander V. (Moscow, RU); Filippov, Eugene A. (Moscow, RU)

1998-05-12T23:59:59.000Z

127

Processing of solid mixed waste containing radioactive and hazardous materials  

DOE Patents (OSTI)

Apparatus for the continuous heating and melting of a solid mixed waste bearing radioactive and hazardous materials to form separate metallic, slag and gaseous phases for producing compact forms of the waste material to facilitate disposal includes a copper split water-cooled (cold) crucible as a reaction vessel for receiving the waste material. The waste material is heated by means of the combination of a plasma torch directed into the open upper portion of the cold crucible and an electromagnetic flux produced by induction coils disposed about the crucible which is transparent to electromagnetic fields. A metallic phase of the waste material is formed in a lower portion of the crucible and is removed in the form of a compact ingot suitable for recycling and further processing. A glass-like, non-metallic slag phase containing radioactive elements is also formed in the crucible and flows out of the open upper portion of the crucible into a slag ingot mold for disposal. The decomposition products of the organic and toxic materials are incinerated and converted to environmentally safe gases in the melter. 6 figs.

Gotovchikov, V.T.; Ivanov, A.V.; Filippov, E.A.

1998-05-12T23:59:59.000Z

128

System for chemically digesting low level radioactive, solid waste material  

DOE Patents (OSTI)

An improved method and system for chemically digesting low level radioactive, solid waste material having a high through-put. The solid waste material is added to an annular vessel (10) substantially filled with concentrated sulfuric acid. Concentrated nitric acid or nitrogen dioxide is added to the sulfuric acid within the annular vessel while the sulfuric acid is reacting with the solid waste. The solid waste is mixed within the sulfuric acid so that the solid waste is substantilly fully immersed during the reaction. The off gas from the reaction and the products slurry residue is removed from the vessel during the reaction.

Cowan, Richard G. (Kennewick, WA); Blasewitz, Albert G. (Richland, WA)

1982-01-01T23:59:59.000Z

129

Savannah River Site Waste Disposition Project  

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

Terrel J. Spears Terrel J. Spears Assistant Manager Waste Disposition Project DOE Savannah River Operations Office Savannah River Site Savannah River Site Waste Disposition Project Waste Disposition Project 2 Waste Disposition Project - Mission Radioactive Liquid Waste - Tank Waste Stabilization and Disposition - Disposition 36 million gallons of radioactive liquid waste - Close 49 underground storage tanks in which the waste now resides 3 36.7 Million 33.7 Mgal (92%) 3.0 Mgal (8%) Saltcake Sludge Salt Supernate Volume Curies 397 Million Curies (MCi) 212 MCi (54%) 185 MCi (46%) Gallons (Mgal) 36.5 Million 33.5 Mgal (92%) 3.0 Mgal (8%) Liquid Waste Background Liquid Waste Background * 2 tanks closed * 49 tanks remaining to close - aging, carbon steel - 27 compliant, 22 non-compliant - 12 have known leak sites

130

SRS - Programs - Liquid Waste Disposition  

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

Liquid Waste Disposition Liquid Waste Disposition This includes both the solidification of highly radioactive liquid wastes stored in SRS's tank farms and disposal of liquid low-level waste generated as a by-product of the separations process and tank farm operations. This low-level waste is treated in the Effluent Treatment Facility. High-activity liquid waste is generated at SRS as by-products from the processing of nuclear materials for national defense, research and medical programs. The waste, totaling about 36 million gallons, is currently stored in 49 underground carbon-steel waste tanks grouped into two "tank farms" at SRS. While the waste is stored in the tanks, it separates into two parts: a sludge that settles on the bottom of the tank, and a liquid supernate that resides on top of the sludge. The waste is reduced to about 30 percent of its original volume by evaporation. The condensed evaporator "overheads" are transferred to the Effluent Treatment Project for final cleanup prior to release to the environment. As the concentrate cools a portion of it crystallizes forming solid saltcake. The concentrated supernate and saltcake are less mobile and therefore less likely to escape to the environment in the event of a tank crack or leak.

131

Best Practices for the Security of Radioactive Materials  

Science Conference Proceedings (OSTI)

This work is funded under a grant provided by the US Department of Health and Human Services, Centers for Disease Control. The Department of Health and Mental Hygiene (DOHMH) awarded a contract to Brookhaven National Laboratory (BNL) to develop best practices guidance for Office of Radiological Health (ORH) licensees to increase on-site security to deter and prevent theft of radioactive materials (RAM). The purpose of this document is to describe best practices available to manage the security of radioactive materials in medical centers, hospitals, and research facilities. There are thousands of such facilities in the United States, and recent studies suggest that these materials may be vulnerable to theft or sabotage. Their malevolent use in a radiological-dispersion device (RDD), viz., a dirty bomb, can have severe environmental- and economic- impacts, the associated area denial, and potentially large cleanup costs, as well as other effects on the licensees and the public. These issues are important to all Nuclear Regulatory Commission and Agreement State licensees, and to the general public. This document outlines approaches for the licensees possessing these materials to undertake security audits to identify vulnerabilities in how these materials are stored or used, and to describe best practices to upgrade or enhance their security. Best practices can be described as the most efficient (least amount of effort/cost) and effective (best results) way of accomplishing a task and meeting an objective, based on repeatable procedures that have proven themselves over time for many people and circumstances. Best practices within the security industry include information security, personnel security, administrative security, and physical security. Each discipline within the security industry has its own 'best practices' that have evolved over time into common ones. With respect to radiological devices and radioactive-materials security, industry best practices encompass both physical security (hardware and engineering) and administrative procedures. Security regimes for these devices and materials typically use a defense-in-depth- or layered-security approach to eliminate single points of failure. The Department of Energy, the Department of Homeland Security, the Department of Defense, the American Society of Industrial Security (ASIS), the Security Industry Association (SIA) and Underwriters Laboratory (UL) all rovide design guidance and hardware specifications. With a graded approach, a physical-security specialist can tailor an integrated security-management system in the most appropriate cost-effective manner to meet the regulatory and non-regulatory requirements of the licensee or client.

Coulter, D.T.; Musolino, S.

2009-05-01T23:59:59.000Z

132

Integrated Facilities Disposition Program  

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

Facilities Facilities Disposition Program Tank Waste Corporate Board Meeting at ORNL Sharon Robinson Dirk Van Hoesen Robert Jubin Brad Patton July 29, 2009 2 Managed by UT-Battelle for the U.S. Department of Energy The Integrated Facility Disposition Program (IFDP) addresses the remaining EM Scope at both ORNL and Y-12 Cost Range: $7 - $14B Schedule: 26 Years 3 Managed by UT-Battelle for the U.S. Department of Energy Scope of work * Treatment and disposition of legacy materials and waste * D&D 327 (1.5 M ft 2 ) excess facilities generating >2 M yd 3 debris * Soil and groundwater remedial actions generating >1 M yd 3 soils * Facilities surveillance and maintenance * Reconfiguration of waste management facilities * Ongoing waste management operations * Project management

133

THERMAL UPGRADING OF 9977 RADIOACTIVE MATERIAL (RAM) TYPE B PACKAGE  

Science Conference Proceedings (OSTI)

The 9977 package is a radioactive material package that was originally certified to ship Heat Sources and RTG contents up to 19 watts and it is now being reviewed to significantly expand its contents in support of additional DOE missions. Thermal upgrading will be accomplished by employing stacked 3013 containers, a 3013 aluminum spacer and an external aluminum sleeve for enhanced heat transfer. The 7th Addendum to the original 9977 package Safety Basis Report describing these modifications is under review for the DOE certification. The analyses described in this paper show that this well-designed and conservatively analyzed package can be upgraded to carry contents with decay heat up to 38 watts with some simple design modifications. The Model 9977 package has been designed as a replacement for the Department of Transportation (DOT) Fissile Specification 6M package. The 9977 package is a very versatile Type B package which is certified to transport and store a wide spectrum of radioactive materials. The package was analyzed quite conservatively to increase its usefulness and store different payload configurations. Its versatility is evident from several daughter packages such as the 9978 and H1700, and several addendums where the payloads have been modified to suit the Shipper's needs without additional testing.

Gupta, N.; Abramczyk, G.

2012-03-26T23:59:59.000Z

134

2011 Radioactive Materials Usage Survey for Unmonitored Point Sources  

SciTech Connect

This report provides the results of the 2011 Radioactive Materials Usage Survey for Unmonitored Point Sources (RMUS), which was updated by the Environmental Protection (ENV) Division's Environmental Stewardship (ES) at Los Alamos National Laboratory (LANL). ES classifies LANL emission sources into one of four Tiers, based on the potential effective dose equivalent (PEDE) calculated for each point source. Detailed descriptions of these tiers are provided in Section 3. The usage survey is conducted annually; in odd-numbered years the survey addresses all monitored and unmonitored point sources and in even-numbered years it addresses all Tier III and various selected other sources. This graded approach was designed to ensure that the appropriate emphasis is placed on point sources that have higher potential emissions to the environment. For calendar year (CY) 2011, ES has divided the usage survey into two distinct reports, one covering the monitored point sources (to be completed later this year) and this report covering all unmonitored point sources. This usage survey includes the following release points: (1) all unmonitored sources identified in the 2010 usage survey, (2) any new release points identified through the new project review (NPR) process, and (3) other release points as designated by the Rad-NESHAP Team Leader. Data for all unmonitored point sources at LANL is stored in the survey files at ES. LANL uses this survey data to help demonstrate compliance with Clean Air Act radioactive air emissions regulations (40 CFR 61, Subpart H). The remainder of this introduction provides a brief description of the information contained in each section. Section 2 of this report describes the methods that were employed for gathering usage survey data and for calculating usage, emissions, and dose for these point sources. It also references the appropriate ES procedures for further information. Section 3 describes the RMUS and explains how the survey results are organized. The RMUS Interview Form with the attached RMUS Process Form(s) provides the radioactive materials survey data by technical area (TA) and building number. The survey data for each release point includes information such as: exhaust stack identification number, room number, radioactive material source type (i.e., potential source or future potential source of air emissions), radionuclide, usage (in curies) and usage basis, physical state (gas, liquid, particulate, solid, or custom), release fraction (from Appendix D to 40 CFR 61, Subpart H), and process descriptions. In addition, the interview form also calculates emissions (in curies), lists mrem/Ci factors, calculates PEDEs, and states the location of the critical receptor for that release point. [The critical receptor is the maximum exposed off-site member of the public, specific to each individual facility.] Each of these data fields is described in this section. The Tier classification of release points, which was first introduced with the 1999 usage survey, is also described in detail in this section. Section 4 includes a brief discussion of the dose estimate methodology, and includes a discussion of several release points of particular interest in the CY 2011 usage survey report. It also includes a table of the calculated PEDEs for each release point at its critical receptor. Section 5 describes ES's approach to Quality Assurance (QA) for the usage survey. Satisfactory completion of the survey requires that team members responsible for Rad-NESHAP (National Emissions Standard for Hazardous Air Pollutants) compliance accurately collect and process several types of information, including radioactive materials usage data, process information, and supporting information. They must also perform and document the QA reviews outlined in Section 5.2.6 (Process Verification and Peer Review) of ES-RN, 'Quality Assurance Project Plan for the Rad-NESHAP Compliance Project' to verify that all information is complete and correct.

Sturgeon, Richard W. [Los Alamos National Laboratory

2012-06-27T23:59:59.000Z

135

2011 Radioactive Materials Usage Survey for Unmonitored Point Sources  

SciTech Connect

This report provides the results of the 2011 Radioactive Materials Usage Survey for Unmonitored Point Sources (RMUS), which was updated by the Environmental Protection (ENV) Division's Environmental Stewardship (ES) at Los Alamos National Laboratory (LANL). ES classifies LANL emission sources into one of four Tiers, based on the potential effective dose equivalent (PEDE) calculated for each point source. Detailed descriptions of these tiers are provided in Section 3. The usage survey is conducted annually; in odd-numbered years the survey addresses all monitored and unmonitored point sources and in even-numbered years it addresses all Tier III and various selected other sources. This graded approach was designed to ensure that the appropriate emphasis is placed on point sources that have higher potential emissions to the environment. For calendar year (CY) 2011, ES has divided the usage survey into two distinct reports, one covering the monitored point sources (to be completed later this year) and this report covering all unmonitored point sources. This usage survey includes the following release points: (1) all unmonitored sources identified in the 2010 usage survey, (2) any new release points identified through the new project review (NPR) process, and (3) other release points as designated by the Rad-NESHAP Team Leader. Data for all unmonitored point sources at LANL is stored in the survey files at ES. LANL uses this survey data to help demonstrate compliance with Clean Air Act radioactive air emissions regulations (40 CFR 61, Subpart H). The remainder of this introduction provides a brief description of the information contained in each section. Section 2 of this report describes the methods that were employed for gathering usage survey data and for calculating usage, emissions, and dose for these point sources. It also references the appropriate ES procedures for further information. Section 3 describes the RMUS and explains how the survey results are organized. The RMUS Interview Form with the attached RMUS Process Form(s) provides the radioactive materials survey data by technical area (TA) and building number. The survey data for each release point includes information such as: exhaust stack identification number, room number, radioactive material source type (i.e., potential source or future potential source of air emissions), radionuclide, usage (in curies) and usage basis, physical state (gas, liquid, particulate, solid, or custom), release fraction (from Appendix D to 40 CFR 61, Subpart H), and process descriptions. In addition, the interview form also calculates emissions (in curies), lists mrem/Ci factors, calculates PEDEs, and states the location of the critical receptor for that release point. [The critical receptor is the maximum exposed off-site member of the public, specific to each individual facility.] Each of these data fields is described in this section. The Tier classification of release points, which was first introduced with the 1999 usage survey, is also described in detail in this section. Section 4 includes a brief discussion of the dose estimate methodology, and includes a discussion of several release points of particular interest in the CY 2011 usage survey report. It also includes a table of the calculated PEDEs for each release point at its critical receptor. Section 5 describes ES's approach to Quality Assurance (QA) for the usage survey. Satisfactory completion of the survey requires that team members responsible for Rad-NESHAP (National Emissions Standard for Hazardous Air Pollutants) compliance accurately collect and process several types of information, including radioactive materials usage data, process information, and supporting information. They must also perform and document the QA reviews outlined in Section 5.2.6 (Process Verification and Peer Review) of ES-RN, 'Quality Assurance Project Plan for the Rad-NESHAP Compliance Project' to verify that all information is complete and correct.

Sturgeon, Richard W. [Los Alamos National Laboratory

2012-06-27T23:59:59.000Z

136

Fast Neutron Radioactivity and Damage Studies on Materials  

SciTech Connect

Many materials and electronics need to be tested for the radiation environment expected at linear colliders (LC) to improve reliability and longevity since both accelerator and detectors will be subjected to large fluences of hadrons, leptons and gammas. Examples include NdFeB magnets, considered for the damping rings, injection and extraction lines and final focus, electronic and electro-optic devices to be utilized in detector readout, accelerator controls and the CCDs required for the vertex detector, as well as high and low temperature superconducting materials (LTSMs) because some magnets will be superconducting. Our first measurements of fast neutron, stepped doses at the UC Davis McClellan Nuclear Reactor Center (UCD MNRC) were presented for NdFeB materials at EPAC04 where the damage appeared proportional to the distances between the effective operating point and Hc. We have extended those doses, included other manufacturer's samples and measured induced radioactivities. We have also added L and HTSMs as well as a variety of relevant semiconductor and electro-optic materials including PBG fiber that we studied previously only with gamma rays.

Anderson, S.; Spencer, J.; Wolf, Z.; /SLAC; Gallagher, G.; Pellett, D.; Boussoufi, M.; /UC, Davis; Volk, J.; /Fermilab

2007-07-23T23:59:59.000Z

137

SEM Facility for Examination of Reactive and Radioactive Materials  

SciTech Connect

A scanning electron microscope (SEM) facility for the examination of tritium-containing materials is operational at Mound Laboratory. The SEM is installed with the sample chamber incorporated as an integral part of an inert gas glovebox facility to enable easy handling of radioactive and pyrophoric materials. A standard SEM (ETEC Model B-1) was modified to meet dimensional, operational, and safety-related requirements. A glovebox was designed and fabricated which permitted access with the gloves to all parts of the SEM sample chamber to facilitate detector and accessory replacement and repairs. A separate console combining the electron optical column and specimen chamber was interfaced to the glovebox by a custom-made, neoprene bellows so that the vibrations normally associated with the blowers and pumps were damped. Photomicrographs of tritiated pyrophoric materials show the usefulness of this facility. Some of the difficulties involved in the investigation of these materials are also discussed. The SEM is also equipped with an energy dispersive X-ray detector (ORTEC) and a Secondary Ion Mass Spectrometer (3M) attachments. This latter attachment allows analysis of secondary ions with masses ranging from 1-300 amu.

Downs, G. L.; Tucker, P. A.

1973-06-01T23:59:59.000Z

138

Priorities for technology development and policy to reduce the risk from radioactive materials.  

Science Conference Proceedings (OSTI)

The Standing Committee on International Security of Radioactive and Nuclear Materials in the Nonproliferation and Arms Control Division conducted its fourth annual workshop in February 2010 on Reducing the Risk from Radioactive and Nuclear Materials. This workshop examined new technologies in real-time tracking of radioactive materials, new risks and policy issues in transportation security, the best practices and challenges found in addressing illicit radioactive materials trafficking, industry leadership in reducing proliferation risk, and verification of the Nuclear Nonproliferation Treaty, Article VI. Technology gaps, policy gaps, and prioritization for addressing the identified gaps were discussed. Participants included academia, policy makers, radioactive materials users, physical security and safeguards specialists, and vendors of radioactive sources and transportation services. This paper summarizes the results of this workshop with the recommendations and calls to action for the Institute of Nuclear Materials Management (INMM) membership community.

Duggan, Ruth Ann

2010-06-01T23:59:59.000Z

139

Is anyone regulating naturally occurring radioactive material? A state survey  

SciTech Connect

As far as we know, naturally occurring radioactive material (NORM) has surrounded humankind since the beginning of time. However, recent data demonstrating that certain activities concentrate NORM have increased concern regarding its proper handling and disposal and precipitated the development of new NORM-related regulations. The regulation of NORM affects the management of government facilities as well as a broad range of industrial processes. Recognizing that NORM regulation at the federal level is extremely limited, Argonne National Laboratory (ANL) conducted a 50-state survey to determine the extent to which states have assumed the responsibility for regulating NORM as well as the NORM standards that are currently being applied at the state level. Though the survey indicates that NORM regulation comprises a broad spectrum of controls from full licensing requirements to virtually no regulation at afl, a trend is emerging toward recognition of the need for increased regulation of potential NORM hazards, particularly in the absence of federal standards.

Gross, E.M.; Barisas, S.G.

1993-08-01T23:59:59.000Z

140

THERMAL PERFORMANCE OF RADIOACTIVE MATERIAL PACKAGES IN TRANSPORT CONFIGURATION  

SciTech Connect

Drum type packages are routinely used to transport radioactive material (RAM) in the U.S. Department of Energy (DOE) complex. These packages are designed to meet the federal regulations described in 10 CFR Part 71. The packages are transported in specially designed vehicles like Safe Secure Transport (SST) for safety and security. In the transport vehicles, the packages are placed close to each other to maximize the number of units in the vehicle. Since the RAM contents in the packagings produce decay heat, it is important that they are spaced sufficiently apart to prevent overheating of the containment vessel (CV) seals and the impact limiter to ensure the structural integrity of the package. This paper presents a simple methodology to assess thermal performance of a typical 9975 packaging in a transport configuration.

Gupta, N.

2010-03-04T23:59:59.000Z

Note: This page contains sample records for the topic "disposition radioactive materials" 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

Numerical estimation on free electrons generated by shielded radioactive materials under various gaseous environments  

SciTech Connect

We report simulation results on generation of free electrons due to the presence of radioactive materials under controlled pressure and gases using a general Monte Carlo transport code (MCNPX). A radioactive material decays to lower atomic number, simultaneously producing high energy gamma rays that can generate free electrons via various scattering mechanisms. This paper shows detailed simulation works for answering how many free electrons can be generated under the existence of shielded radioactive materials as a function of pressure and types of gases.

Kim, D. S. [Department of Physics, Ulsan National Institute of Science and Technology (UNIST), Ulsan 689-798 (Korea, Republic of); Lee, W. S.; So, J. H. [Agency for Defence Development (ADD), Daejeon 305-152 (Korea, Republic of); Choi, E. M. [Department of Physics, Ulsan National Institute of Science and Technology (UNIST), Ulsan 689-798 (Korea, Republic of); School of Electrical and Computer Engineering, Ulsan National Institute of Science and Technology (UNIST), Ulsan 689-798 (Korea, Republic of)

2013-06-15T23:59:59.000Z

142

Source holder collimator for encapsulating radioactive material and collimating the emanations from the material  

DOE Patents (OSTI)

This invention provides a transportable device capable of detecting normal levels of a trace element, such as lead in a doughnutshaped blood sample by x-ray fluorescence with a minimum of sample preparation in a relatively short analyzing time. In one embodiment, the blood is molded into a doughnut-shaped sample around an annular array of low-energy radioactive material that is at the center of the doughnut-shaped sample but encapsulated in a collimator, the latter shielding a detector that is close to the sample and facing the same so that the detector receives secondary emissions from the sample while the collimator collimates ths primary emissions from the radioactive material to direct these emissions toward the sample around 360 deg and away from the detector. (Official Gazette)

Laurer, G.R.

1974-01-22T23:59:59.000Z

143

Inelastic analysis acceptance criteria for radioactive material transportation containers  

SciTech Connect

The design criteria currently used in the design of radioactive material (RAM) transportation containers are taken from the ASME Boiler and Pressure Vessel Code (ASME, 1992). These load-based criteria are ideally suited for pressure vessels where the loading is quasistatic and all stresses are in equilibrium with externally applied loads. For impact events, the use of load-based criteria is less supportable. Impact events tend to be energy controlled, and thus, energy-based acceptance criteria would appear to be more appropriate. Determination of an ideal design criteria depends on what behavior is desired. Currently there is not a design criteria for inelastic analysis for RAM nation packages that is accepted by the regulatory agencies. This lack of acceptance criteria is one of the major factors in limiting the use of inelastic analysis. In this paper inelastic analysis acceptance criteria based on stress and strain-energy density will be compared for two stainless steel test units subjected to impacts onto an unyielding target. Two different material models are considered for the inelastic analysis, a bilinear fit of the stress-strain curve and a power law hardening model that very closely follows the stress-strain curve. It is the purpose of this paper to stimulate discussion and research into the area of strain-energy density based inelastic analysis acceptance criteria.

Ammerman, D.J.; Ludwigsen, J.S.

1993-06-01T23:59:59.000Z

144

Plutonium Disposition Program | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Plutonium Disposition Program Plutonium Disposition Program Home > About Us > Our Programs > Nonproliferation > Fissile Materials Disposition > Plutonium Disposition Program Plutonium Disposition Program The U.S.-Russia Plutonium Management and Disposition Agreement (PMDA), which entered into force on July 13, 2011, commits each country to dispose of at least 34 metric tons (MT) of weapon-grade plutonium withdrawn from their respective nuclear weapon programs. The U.S. remains firmly committed to its PMDA obligation to dispose of excess weapons plutonium. U.S. Plutonium Disposition The current U.S. plan to dispose of 34 MT of weapon-grade plutonium is to fabricate it into Mixed Oxide (MOX) fuel and irradiate it in existing light water reactors. This approach requires construction of new facilities

145

Disposition of excess highly enriched uranium status and update  

SciTech Connect

This paper presents the status of the US DOE program charged with the disposition of excess highly enriched uranium (HEU). Approximately 174 metric tonnes of HEU, with varying assays above 20 percent, has been declared excess from US nuclear weapons. A progress report on the identification and characterization of specific batches of excess HEU is provided, and plans for processing it into commercial nuclear fuel or low-level radioactive waste are described. The resultant quantities of low enriched fuel material expected from processing are given, as well as the estimated schedule for introducing the material into the commercial reactor fuel market. 2 figs., 3 tabs.

Williams, C.K. III; Arbital, J.G.

1997-09-01T23:59:59.000Z

146

EIS-0240: Disposition of Surplus Highly Enriched Uranium  

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

The Department proposes to eliminate the proliferation threat of surplus highly enriched uranium (HEU) by blending it down to low enriched uranium (LEU), which is not weapons-usable. The EIS assesses the disposition of a nominal 200 metric tons of surplus HEU. The Preferred Alternative is, where practical, to blend the material for use as LEU and use overtime, in commercial nuclear reactor field to recover its economic value. Material that cannot be economically recovered would be blended to LEU for disposal as low-level radioactive waste.

147

PTS 13.1 Radioactive And Hazardous Material Transportation 4/13/00 |  

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

PTS 13.1 Radioactive And Hazardous Material Transportation 4/13/00 PTS 13.1 Radioactive And Hazardous Material Transportation 4/13/00 PTS 13.1 Radioactive And Hazardous Material Transportation 4/13/00 The objective of this surveillance is to evaluate the effectiveness of the contractor's programs, policies, and procedures to transport radioactive and hazardous materials off-site or to receive such materials for routine operations, treatment, storage, or disposal. The Facility Representative observes preparation of materials for shipment and receipt of materials and reviews specific documents to determine compliance with requirements imposed by DOE and by applicable regulations from the U.S. Nuclear Regulatory Commission and the Department of Transportation. PTS13-01.doc More Documents & Publications Order Module--DOE O 460.1C, PACKAGING AND TRANSPORTATION SAFETY, DOE O

148

DOE/EA-1651: FINDING OF NO SIGNIFICANT IMPACT Uranium-233 Material Downblending and Disposition Project at the Oak Ridge National Laboratory, Oak Ridge, Tennessee (01/13/10)  

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

URANIUM-233 MATERIAL DOWNBLENDING AND DISPOSITION PROJECT URANIUM-233 MATERIAL DOWNBLENDING AND DISPOSITION PROJECT AT THE OAK RIDGE NATIONAL LABORATORY, OAK RIDGE, TENNESSEE AGENCY: U.S. Department of Energy (DOE) ACTION: Finding of No Significant Impact (FONSI) SUMMARY: DOE has completed the Final Environmental Assessment for U-233 Material Downblending and Disposition Project at the Oak Ridge National Laboratory [DOE/EA-1651]. This environmental assessment (EA) evaluates the impacts of planned activities to modify selected Oak Ridge National Laboratory (ORNL) facilities; process the ORNL inventory of uranium-233 (U-233); and transport the processed material to a long-term disposal facility. Small quantities of similar material currently stored at other DOE sites may also be included in this initiative. The

149

U.S. Department of Energy Guidelines for Residual Radioactive Material at  

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

U.S. Department of Energy Guidelines for Residual Radioactive U.S. Department of Energy Guidelines for Residual Radioactive Material at Formerly Utilized Sites Remedial Action Program and Remote Surplus Facilities Management Program Sites U.S. Department of Energy Guidelines for Residual Radioactive Material at Formerly Utilized Sites Remedial Action Program and Remote Surplus Facilities Management Program Sites U.S. Department of Energy Guidelines for Residual Radioactive Material at Formerly Utilized Sites Remedial Action Program and Remote Surplus Facilities Management Program Sites (Revision 2, March 1987) U.S. Department of Energy Guidelines for Residual Radioactive Material at Formerly Utilized Sites Remedial Action Program and Remote Surplus Facilities Management Program Sites (Revision 2, March 1987) More Documents & Publications

150

U.S. Department of Energy Guidelines for Residual Radioactive Material at  

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

U.S. Department of Energy Guidelines for Residual Radioactive U.S. Department of Energy Guidelines for Residual Radioactive Material at Formerly Utilized Sites Remedial Action Program and Remote Surplus Facilities Management Program Sites U.S. Department of Energy Guidelines for Residual Radioactive Material at Formerly Utilized Sites Remedial Action Program and Remote Surplus Facilities Management Program Sites U.S. Department of Energy Guidelines for Residual Radioactive Material at Formerly Utilized Sites Remedial Action Program and Remote Surplus Facilities Management Program Sites (Revision 2, March 1987) U.S. Department of Energy Guidelines for Residual Radioactive Material at Formerly Utilized Sites Remedial Action Program and Remote Surplus Facilities Management Program Sites (Revision 2, March 1987) More Documents & Publications

151

RELEASE OF DRIED RADIOACTIVE WASTE MATERIALS TECHNICAL BASIS DOCUMENT  

Science Conference Proceedings (OSTI)

This technical basis document was developed to support RPP-23429, Preliminary Documented Safety Analysis for the Demonstration Bulk Vitrification System (PDSA) and RPP-23479, Preliminary Documented Safety Analysis for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Facility. The main document describes the risk binning process and the technical basis for assigning risk bins to the representative accidents involving the release of dried radioactive waste materials from the Demonstration Bulk Vitrification System (DBVS) and to the associated represented hazardous conditions. Appendices D through F provide the technical basis for assigning risk bins to the representative dried waste release accident and associated represented hazardous conditions for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Packaging Unit (WPU). The risk binning process uses an evaluation of the frequency and consequence of a given representative accident or represented hazardous condition to determine the need for safety structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls. A representative accident or a represented hazardous condition is assigned to a risk bin based on the potential radiological and toxicological consequences to the public and the collocated worker. Note that the risk binning process is not applied to facility workers because credible hazardous conditions with the potential for significant facility worker consequences are considered for safety-significant SSCs and/or TSR-level controls regardless of their estimated frequency. The controls for protection of the facility workers are described in RPP-23429 and RPP-23479. Determination of the need for safety-class SSCs was performed in accordance with DOE-STD-3009-94, Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses, as described below.

KOZLOWSKI, S.D.

2007-05-30T23:59:59.000Z

152

RESRAD-RECYCLE : a computer model for analyzing radiation exposures resulting from recycling radioactively contaminated scrap metals or reusing ratioactively surface-contaminated materials and equipment.  

Science Conference Proceedings (OSTI)

RESRAD-RECYCLE is a computer code designed by Argonne National Laboratory (ANL) to be used in making decisions about the disposition of radioactively contaminated materials and scrap metals. It implements a pathway analysis methodology to evaluate potential radiation exposures resulting from the recycling of contaminated scrap metals and the reuse of surface-contaminated materials and equipment. For modeling purposes, it divides the entire metal recycling process into six steps: (1) scrap delivery, (2) scrap melting, (3) ingot delivery, (4) product fabrication, (5) product distribution, and (6) use of finished product. RESRAD-RECYCLE considers the reuse of surface-contaminated materials in their original forms. It contains representative exposure scenarios for each recycling step and the reuse process; users can also specify scenarios if desired. The model calculates individual and collective population doses for workers involved in the recycling process and for the public using the finished products. The results are then used to derive clearance levels for the contaminated materials on the basis of input dose restrictions. The model accounts for radiological decay and ingrowth, dilution and partitioning during melting, and distribution of refined metal in the various finished products, as well as the varying densities and geometries of the radiation sources during the recycling process. A complete material balance in terms of mass and radioactivity during the recycling process can also be implemented. In an international validation study, the radiation doses calculated by RESRAD-RECYCLE were shown to agree fairly well with actual measurement data.

Cheng, J. J.; Kassas, B.; Yu, C.; Arnish, J. J.; LePoire, D.; Chen, S.-Y.; Williams, W. A.; Wallo, A.; Peterson, H.; Environmental Assessment; DOE; Univ. of Texas

2004-11-01T23:59:59.000Z

153

Materials and Security Consolidation Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

Science Conference Proceedings (OSTI)

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Security Consolidation Center facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

Not Listed

2011-09-01T23:59:59.000Z

154

Materials and Fuels Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

SciTech Connect

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Fuels Complex facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

Lisa Harvego; Brion Bennett

2011-09-01T23:59:59.000Z

155

Surveillance Guides - PTS 13.1 Radioactive And Hazardous Material Transportation  

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

RADIOACTIVE AND HAZARDOUS MATERIALS TRANSPORTATION RADIOACTIVE AND HAZARDOUS MATERIALS TRANSPORTATION 1.0 Objective The objective of this surveillance is to evaluate the effectiveness of the contractor's programs, policies, and procedures to transport radioactive and hazardous materials off-site or to receive such materials for routine operations, treatment, storage, or disposal. The Facility Representative observes preparation of materials for shipment and receipt of materials and reviews specific documents to determine compliance with requirements imposed by DOE and by applicable regulations from the U.S. Nuclear Regulatory Commission and the Department of Transportation. 2.0 References DOE O 460.1A, Packaging and Transportation Safety DOE O 460.2, Chg1, Departmental Materials Transportation and Packaging

156

Ion-exchange material and method of storing radioactive wastes  

DOE Patents (OSTI)

A new cation exchanger is a modified tobermorite containing aluminum isomorphously substituted for silicon and containing sodium or potassium. The exchanger is selective for lead, rubidium, cobalt, and cadmium and is selective for cesium over calcium or sodium. The tobermorites are compatible with cement and are useful for the long-term fixation and storage of radioactive nuclear wastes.

Komarneni, S.; Roy, D.M.

1983-10-31T23:59:59.000Z

157

ENVIRONMENTALLY SOUND DISPOSAL OF RADIOACTIVE MATERIALS AT A RCRA HAZARDOUS WASTE DISPOSAL FACILITY  

SciTech Connect

The use of hazardous waste disposal facilities permitted under the Resource Conservation and Recovery Act (''RCRA'') to dispose of low concentration and exempt radioactive materials is a cost-effective option for government and industry waste generators. The hazardous and PCB waste disposal facility operated by US Ecology Idaho, Inc. near Grand View, Idaho provides environmentally sound disposal services to both government and private industry waste generators. The Idaho facility is a major recipient of U.S. Army Corps of Engineers FUSRAP program waste and received permit approval to receive an expanded range of radioactive materials in 2001. The site has disposed of more than 300,000 tons of radioactive materials from the federal government during the past five years. This paper presents the capabilities of the Grand View, Idaho hazardous waste facility to accept radioactive materials, site-specific acceptance criteria and performance assessment, radiological safety and environmental monitoring program information.

Romano, Stephen; Welling, Steven; Bell, Simon

2003-02-27T23:59:59.000Z

158

Savannah River Site Experiences in In Situ Field Measurements of Radioactive Materials  

Science Conference Proceedings (OSTI)

This paper discusses some of the field gamma-ray measurements made at the Savannah River Site, the equipment used for the measurements, and lessons learned during in situ identification and characterization of radioactive materials.

Moore, F.S.

1999-10-07T23:59:59.000Z

159

Compilation of current literature on seals, closures, and leakage for radioactive material packagings  

SciTech Connect

This report presents an overview of the features that affect the sealing capability of radioactive material packagings currently certified by the US Nuclear Regulatory Commission. The report is based on a review of current literature on seals, closures, and leakage for radioactive material packagings. Federal regulations that relate to the sealing capability of radioactive material packagings, as well as basic equations for leakage calculations and some of the available leakage test procedures are presented. The factors which affect the sealing capability of a closure, including the properties of the sealing surfaces, the gasket material, the closure method and the contents are discussed in qualitative terms. Information on the general properties of both elastomer and metal gasket materials and some specific designs are presented. A summary of the seal material, closure method, and leakage tests for currently certified packagings with large diameter seals is provided. 18 figs., 9 tabs.

Warrant, M.M.; Ottinger, C.A.

1989-01-01T23:59:59.000Z

160

BIOLOGICAL EVIDENCE disposition process  

Science Conference Proceedings (OSTI)

... Notification of destruction sent per statutory requirements In-house tickler system tracks evidence and identifies upcoming disposition time ...

2013-05-14T23:59:59.000Z

Note: This page contains sample records for the topic "disposition radioactive materials" 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.


161

EIS-0327: Disposition of Scrap Metals Programmatic EIS  

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

This EIS will evaluate the environmental impacts of policy alternatives for the disposition of scrap metals (primarily carbon steel and stainless steel) that may have residual surface radioactivity. DOE is cancelling this EIS.

162

Shipment of Small Quantities of Unspecified Radioactive Material in Chalfant Packagings  

SciTech Connect

In the post 6M era, radioactive materials package users are faced with the disciplined operations associated with use of Certified Type B packagings. Many DOE, commercial and academic programs have a requirement to ship and/or store small masses of poorly characterized or unspecified radioactive material. For quantities which are small enough to be fissile exempt and have low radiation levels, the materials could be transported in a package which provides the required containment level. Because their Chalfant type containment vessels meet the highest standard of containment (helium leak-tight), the 9975, 9977, and 9978 are capable of transporting any of these contents. The issues associated with certification of a high-integrity, general purpose package for shipping small quantities of unspecified radioactive material are discussed and certification of the packages for this mission is recommended.

Smith, Allen; Abramczyk, Glenn; Nathan, Steven; Bellamy, Steve

2009-06-12T23:59:59.000Z

163

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

164

A SUMMARY OF INCIDENTS INVOLVING USAEC SHIPMENTS OF RADIOACTIVE MATERIAL, 1957-1961  

SciTech Connect

Data are summarized on incidents that have been sustained by the AEC in the transport of radioactive materials from 1957 through 1981. In the period covered by this report there were 47 incidents reported. Twenty-nine did not result in the release of radioactive materials. Of the remaining 18 cases there was none that involved any serious radiological consequences or involved costly cleanup. Six of the incidents involved onsite movements of materials. The incidents are classified in accordance with the type of radiation release that occurred, mode of transport, and type of incident. Photographs are included for a number of the incidents. (C.H.)

Patterson, D.E.; DeFatta, V.P.

1963-10-31T23:59:59.000Z

165

ESTIMATING IMPURITIES IN SURPLUS PLUTONIUM FOR DISPOSITION  

Science Conference Proceedings (OSTI)

The United States holds at least 61.5 metric tons (MT) of plutonium that is permanently excess to use in nuclear weapons programs, including 47.2 MT of weapons-grade plutonium. Surplus inventories will be stored safely by the Department of Energy (DOE) and then transferred to facilities that will prepare the plutonium for permanent disposition. The Savannah River National Laboratory (SRNL) operates a Feed Characterization program for the Office of Fissile Materials Disposition of the National Nuclear Security Administration and the DOE Office of Environmental Management. Many of the items that require disposition are only partially characterized, and SRNL uses a variety of techniques to predict the isotopic and chemical properties that are important for processing through the Mixed Oxide Fuel Fabrication Facility and alternative disposition paths. Recent advances in laboratory tools, including Prompt Gamma Analysis and Peroxide Fusion treatment, provide data on the existing inventories that will enable disposition without additional, costly sampling and destructive analysis.

Allender, J.; Moore, E.

2013-07-17T23:59:59.000Z

166

U.S. DEPARTMENT OF ENERGY GUIDELINES FOR RESIDUAL RADIOACTIVE MATERIAL AT  

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

I I U.S. DEPARTMENT OF ENERGY GUIDELINES FOR RESIDUAL RADIOACTIVE MATERIAL AT FORMERLY UTILIZED SITES REMEDIAL ACTION PROGRAM AHD REMOTE SURPLUS FACILITIES MANAGEMENT PROGRAM SITES (Revision 2, March 1987) A. INTRODUCTION This document presents U.S. Department of Energy (DOE) radiological protection guidelines for cleanup of residual radioactive material and management of the resulting wastes and residues. It is applicable to si~es - "C-- identified by the Formerly Utilized Sites l{emedia1 Ac:tionProgram (FUSRAP) .and remote sites identified by the Surplus Facilities Management Program (SFMP).* The topics covered are basic dose limits, guidelines and authorized limits for allowable levels of residual radioactive material, and requirements for

167

Method for acid oxidation of radioactive, hazardous, and mixed organic waste materials  

DOE Patents (OSTI)

The present invention is directed to a process for reducing the volume of low level radioactive and mixed waste to enable the waste to be more economically stored in a suitable repository, and for placing the waste into a form suitable for permanent disposal. The invention involves a process for preparing radioactive, hazardous, or mixed waste for storage by contacting the waste starting material containing at least one organic carbon-containing compound and at least one radioactive or hazardous waste component with nitric acid and phosphoric acid simultaneously at a contacting temperature in the range of about 140.degree. C. to about 210 .degree. C. for a period of time sufficient to oxidize at least a portion of the organic carbon-containing compound to gaseous products, thereby producing a residual concentrated waste product containing substantially all of said radioactive or inorganic hazardous waste component; and immobilizing the residual concentrated waste product in a solid phosphate-based ceramic or glass form.

Pierce, Robert A. (Aiken, SC); Smith, James R. (Corrales, NM); Ramsey, William G. (Aiken, SC); Cicero-Herman, Connie A. (Aiken, SC); Bickford, Dennis F. (Folly Beach, SC)

1999-01-01T23:59:59.000Z

168

Radiological surveys of properties contaminated by residual radioactive materials from uranium processing sites  

Science Conference Proceedings (OSTI)

This report examines methods for determining the extent and nature of contamination on properties contaminated by residual radioactive materials from uranium processing sites. Methods are also examined for verifying the success of remedial actions in removing the residual radioactive materials. Using literature review and practical experiences from the Edgemont, South Dakota survey program a critical review is made of sampling programs, instrumentation, analytical procedures, data reporting format, and statistical analyses of data. Protocols are recommended for measuring indoor and outdoor gamma-ray exposure rates, surface and subsurface Radium-226 concentrations in soil, and radon daughter concentrations.

Young, J.A.; Jackson, P.O.; Thomas, V.W.

1983-06-01T23:59:59.000Z

169

EA-1599: Disposition of Radioactively Contaminated Nickel Located at the East Tennessee Technology Park, Oak Ridge, Tennessee, and the Paducah Gaseous Diffusion Plant, Paducah, Kentucky, for Controlled Radiological Applications  

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

This EA was being prepared to evaluate potential environmental impacts of a proposal to dispose of nickel scrap that is volumetrically contaminated with radioactive materials and that DOE recovered from equipment it had used in uranium enrichment. This EA is on hold.

170

Health Physics Society Specialists in Radiation Safety Consumer Products Containing Radioactive Materials  

E-Print Network (OSTI)

Everything we encounter in our daily lives contains some radioactive material, some naturally occurring and some man-made: the air we breathe, the water we drink, the food we eat, the ground we walk upon, and the consumer products we purchase and use. Although many might be familiar with the use of radiation to diagnose disease and treat cancer, some people, when they hear the terms radioactive and radiation, might recall images of mushroom clouds or monster mutants that inhabit the world of science fiction movies and comic books. Unfortunately, those false images can cause inordinate fear that is not justified regarding low levels of radioactive material. Many consumer items containing naturally occurring radioactivity can be safely used. This fact sheet describes a photo courtesy of Ray Johnson few of the more commonly encountered and familiar consumer products. Included are the items that can contain sufficient radioactive material to be distinguished from the general environmental background radiation with a simple handheld radiation survey meter. Smoke Detectors Most residential smoke detectors contain a low-activity

unknown authors

2010-01-01T23:59:59.000Z

171

REAL-TIME IDENTIFICATION AND CHARACTERIZATION OF ASBESTOS AND CONCRETE MATERIALS WITH RADIOACTIVE CONTAMINATION  

SciTech Connect

Concrete and asbestos-containing materials were widely used in DOE building construction in the 1940s and 1950s. Over the years, many of these porous materials have been contaminated with radioactive sources, on and below the surface. To improve current practice in identifying hazardous materials and in characterizing radioactive contamination, an interdisciplinary team from Rensselaer has conducted research in two aspects: (1) to develop terahertz time-domain spectroscopy and imaging system that can be used to analyze environmental samples such as asbestos in the field, and (2) to develop algorithms for characterizing the radioactive contamination depth profiles in real-time in the field using gamma spectroscopy. The basic research focused on the following: (1) mechanism of generating of broadband pulsed radiation in terahertz region, (2) optimal free-space electro-optic sampling for asbestos, (3) absorption and transmission mechanisms of asbestos in THz region, (4) the role of asbestos sample conditions on the temporal and spectral distributions, (5) real-time identification and mapping of asbestos using THz imaging, (7) Monte Carlo modeling of distributed contamination from diffusion of radioactive materials into porous concrete and asbestos materials, (8) development of unfolding algorithms for gamma spectroscopy, and (9) portable and integrated spectroscopy systems for field testing in DOE. Final results of the project show that the combination of these innovative approaches has the potential to bring significant improvement in future risk reduction and cost/time saving in DOE's D and D activities.

XU, X. George; Zhang, X.C.

2002-05-10T23:59:59.000Z

172

Fluorescent Functionalized Mesoporous Silica for Radioactive Material Extraction  

Science Conference Proceedings (OSTI)

Mesoporous silica with covalently bound salicylic acid molecules incorporated in the structure was synthesized with a one-pot, co-condensation reaction at room temperature. The as-synthesized material has a large surface area, uniform particle size, and an ordered pore structure as determined by characterization with transmission electron microscopy, thermal gravimetric analysis, and infrared spectra, etc. Using the strong fluorescence and metal coordination capability of salicylic acid, functionalized mesoporous silica (FMS) was developed to track and extract radionuclide contaminants, such as uranyl [U(VI)] ions encountered in subsurface environments. Adsorption measurements showed a strong affinity of the FMS toward U(VI) with a Kd value of 105 mL/g, which is four orders of magnitude higher than the adsorption of U(VI) onto most of the sediments in natural environments. The new materials have a potential for synergistic environmental monitoring and remediation of the radionuclide U(VI) from contaminated subsurface environments.

Li, Juan; Zhu, Kake; Shang, Jianying; Wang, Donghai; Nie, Zimin; Guo, Ruisong; Liu, Chongxuan; Wang, Zheming; Li, Xiaolin; Liu, Jun

2012-08-01T23:59:59.000Z

173

Gamma motes for detection of radioactive materials in shipping containers  

Science Conference Proceedings (OSTI)

Shipping containers can be effectively monitored for radiological materials using gamma (and neutron) motes in distributed mesh networks. The mote platform is ideal for collecting data for integration into operational management systems required for efficiently and transparently monitoring international trade. Significant reductions in size and power requirements have been achieved for room-temperature cadmium zinc telluride (CZT) gamma detectors. Miniaturization of radio modules and microcontroller units are paving the way for low-power, deeply-embedded, wireless sensor distributed mesh networks.

Harold McHugh; William Quam; Stephan Weeks; Brendan Sever

2007-04-13T23:59:59.000Z

174

Surplus Highly Enriched Uranium Disposition Program plan  

SciTech Connect

The purpose of this document is to provide upper level guidance for the program that will downblend surplus highly enriched uranium for use as commercial nuclear reactor fuel or low-level radioactive waste. The intent of this document is to outline the overall mission and program objectives. The document is also intended to provide a general basis for integration of disposition efforts among all applicable sites. This plan provides background information, establishes the scope of disposition activities, provides an approach to the mission and objectives, identifies programmatic assumptions, defines major roles, provides summary level schedules and milestones, and addresses budget requirements.

1996-10-01T23:59:59.000Z

175

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

176

Radiological dose assessment related to management of naturally occurring radioactive materials generated by the petroleum industry  

Science Conference Proceedings (OSTI)

A preliminary radiological dose assessment related to equipment decontamination, subsurface disposal, landspreading, equipment smelting, and equipment burial was conducted to address concerns regarding the presence of naturally occurring radioactive materials in production waste streams. The assessment evaluated the relative dose of these activities and included a sensitivity analysis of certain input parameters. Future studies and potential policy actions are recommended.

Smith, K.P.; Blunt, D.L.; Williams, G.P.; Tebes, C.L. [Argonne National Lab., IL (United States). Environmental Assessment Div.

1995-05-01T23:59:59.000Z

177

VALIDATION OF COMPUTER MODELS FOR RADIOACTIVE MATERIAL SHIPPING PACKAGES  

Science Conference Proceedings (OSTI)

Computer models are abstractions of physical reality and are routinely used for solving practical engineering problems. These models are prepared using large complex computer codes that are widely used in the industry. Patran/Thermal is such a finite element computer code that is used for solving complex heat transfer problems in the industry. Finite element models of complex problems involve making assumptions and simplifications that depend upon the complexity of the problem and upon the judgment of the analysts. The assumptions involve mesh size, solution methods, convergence criteria, material properties, boundary conditions, etc. that could vary from analyst to analyst. All of these assumptions are, in fact, candidates for a purposeful and intended effort to systematically vary each in connection with the others to determine there relative importance or expected overall effect on the modeled outcome. These kinds of models derive from the methods of statistical science and are based on the principles of experimental designs. These, as all computer models, must be validated to make sure that the output from such an abstraction represents reality [1,2]. A new nuclear material packaging design, called 9977, which is undergoing a certification design review, is used to assess the capability of the Patran/Thermal computer model to simulate 9977 thermal response. The computer model for the 9977 package is validated by comparing its output with the test data collected from an actual thermal test performed on a full size 9977 package. Inferences are drawn by performing statistical analyses on the residuals (test data--model predictions).

Gupta, N; Gene Shine, G; Cary Tuckfield, C

2007-05-07T23:59:59.000Z

178

Data collection handbook to support modeling the impacts of radioactive material in soil  

SciTech Connect

A pathway analysis computer code called RESRAD has been developed for implementing US Department of Energy Residual Radioactive Material Guidelines. Hydrogeological, meteorological, geochemical, geometrical (size, area, depth), and material-related (soil, concrete) parameters are used in the RESRAD code. This handbook discusses parameter definitions, typical ranges, variations, measurement methodologies, and input screen locations. Although this handbook was developed primarily to support the application of RESRAD, the discussions and values are valid for other model applications.

Yu, C.; Cheng, J.J.; Jones, L.G.; Wang, Y.Y.; Faillace, E. [Argonne National Lab., IL (United States). Environmental Assessment and Information Sciences Div.; Loureiro, C. [Minas Gerais Univ., Belo Horizonte, MG (Brazil). Escola de Engenharia; Chia, Y.P. [National Taiwan Univ., Taipei (Taiwan, Province of China). Dept. of Geology

1993-04-01T23:59:59.000Z

179

Materials and Fuels Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

SciTech Connect

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Fuels Complex facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

Lisa Harvego; Brion Bennett

2011-09-01T23:59:59.000Z

180

AGING PERFORMANCE OF VITON GLT O-RINGS IN RADIOACTIVE MATERIAL PACKAGES  

Science Conference Proceedings (OSTI)

Radioactive material packages used for transportation of plutonium-bearing materials often contain multiple O-ring seals for containment. Packages such as the Model 9975 are also being used for interim storage of Pu-bearing materials at the Savannah River Site (SRS). One of the seal materials used in such packages is Viton{reg_sign} GLT fluoroelastomer. The aging behavior of containment vessel O-rings based on Viton{reg_sign} GLT at long-term containment term storage conditions is being characterized to assess its performance in such applications. This paper summarizes the program and test results to date.

Skidmore, E; Kerry Dunn, K; Elizabeth Hoffman, E; Elise Fox, E; Kathryn Counts, K

2007-05-07T23:59:59.000Z

Note: This page contains sample records for the topic "disposition radioactive materials" 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

Programmatic Environmental Assessment for the U. S. Department of Energy, Oak Ridge Operations Implementation of a Comprehensive Management Program for the Storage, Transportation, and Disposition of Potentially Reusable Uranium Materials  

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

93 93 FINAL Programmatic Environmental Assessment for the U.S. Department of Energy, Oak Ridge Operations Implementation of a Comprehensive Management Program for the Storage, Transportation, and Disposition of Potentially Reusable Uranium Materials FINDING OF NO SIGNIFICANT IMPMZT PROGR4MMATIC ENVIRONMENTAL ASSESSME?X FOR THE U.S. DEPARTMENT OF ENERGY, OAK RIDGE OPER4TIOSS IMPLEMENTATION OF A COMPREHENSIVE MANAGEMEKT PROGK4hl FOR THE STORAGE, TRANSPORTATION, AND DISPOSITION OF POTENTIALLY REUSABLE URANJUh4 MATERIALS AGEhCY: U.S. DEPARTMENT OF ENERGY (DOE) ACTION: FINDI?iG OF NO SIGNIFICANT 1~IPAC-I SUMI\!L4RY: The U. S. DOE has completed a Programmatic Environmental Assessment (PE:,4) (DOE/E?,- 1393), which is incorporated herein by this reference. Tile purpose of the

182

Excess plutonium disposition: The deep borehole option  

SciTech Connect

This report reviews the current status of technologies required for the disposition of plutonium in Very Deep Holes (VDH). It is in response to a recent National Academy of Sciences (NAS) report which addressed the management of excess weapons plutonium and recommended three approaches to the ultimate disposition of excess plutonium: (1) fabrication and use as a fuel in existing or modified reactors in a once-through cycle, (2) vitrification with high-level radioactive waste for repository disposition, (3) burial in deep boreholes. As indicated in the NAS report, substantial effort would be required to address the broad range of issues related to deep bore-hole emplacement. Subjects reviewed in this report include geology and hydrology, design and engineering, safety and licensing, policy decisions that can impact the viability of the concept, and applicable international programs. Key technical areas that would require attention should decisions be made to further develop the borehole emplacement option are identified.

Ferguson, K.L.

1994-08-09T23:59:59.000Z

183

Hydro-mechanical behaviour of bentonite-based materials used for high-level radioactive waste disposal.  

E-Print Network (OSTI)

??This study deals with the hydro-mechanical behaviour of compacted bentonite-based materials used as sealing materials in high-level radioactive waste repositories. The pure MX80 bentontie, mixtures (more)

Wang, Qiong

2012-01-01T23:59:59.000Z

184

APPLICATION FO FLOW FORMING FOR USE IN RADIOACTIVE MATERIAL PACKAGING DESIGNS  

SciTech Connect

This paper reports on the development and testing performed to demonstrate the use of flow forming as an alternate method of manufacturing containment vessels for use in radioactive material shipping packaging designs. Additionally, ASME Boiler and Pressure Vessel Code, Section III, Subsection NB compliance along with the benefits compared to typical welding of containment vessels will be discussed. SRNL has completed fabrication development and the testing on flow formed containment vessels to demonstrate the use of flow forming as an alternate method of manufacturing a welded 6-inch diameter containment vessel currently used in the 9975 and 9977 radioactive material shipping packaging. Material testing and nondestructive evaluation of the flow formed parts demonstrate compliance to the minimum material requirements specified in applicable parts of ASME Boiler and Pressure Vessel Code, Section II. Destructive burst testing shows comparable results to that of a welded design. The benefits of flow forming as compared to typical welding of containment vessels are significant: dimensional control is improved due to no weld distortion; less final machining; weld fit-up issues associated with pipes and pipe caps are eliminated; post-weld non-destructive testing (i.e., radiography and die penetrant tests) is not necessary; and less fabrication steps are required. Results presented in this paper indicate some of the benefits in adapting flow forming to design of future radioactive material shipping packages containment vessels.

Blanton, P.; Eberl, K.; Abramczyk, G.

2012-07-11T23:59:59.000Z

185

EIS-0327: Disposition of Scrap Metals Programmatic EIS | Department of  

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

27: Disposition of Scrap Metals Programmatic EIS 27: Disposition of Scrap Metals Programmatic EIS EIS-0327: Disposition of Scrap Metals Programmatic EIS Summary This EIS will evaluate the environmental impacts of policy alternatives for the disposition of scrap metals (primarily carbon steel and stainless steel) that may have residual surface radioactivity. DOE is cancelling this EIS. Public Comment Opportunities No public comment opportunities available at this time. Documents Available for Download December 19, 2011 EA-1919: Notice of Revision to Clearance Policy Recycle of Scrap Metals Originating from Radiological Areas (December 2011) July 12, 2001 EIS-0327: Notice of Intent to Prepare a Programmatic Environmental Impact Statement and Announcement of Public Scoping Meetings Disposition of Scrap Metals

186

Radioactive material package closures with the use of shape memory alloys  

SciTech Connect

When heated from room temperature to 165 C, some shape memory metal alloys such as titanium-nickel alloys have the ability to return to a previously defined shape or size with dimensional changes up to 7%. In contrast, the thermal expansion of most metals over this temperature range is about 0.1 to 0.2%. The dimension change of shape memory alloys, which occurs during a martensite to austenite phase transition, can generate stresses as high as 700 MPa (100 kspi). These properties can be used to create a closure for radioactive materials packages that provides for easy robotic or manual operations and results in reproducible, tamper-proof seals. This paper describes some proposed closure methods with shape memory alloys for radioactive material packages. Properties of the shape memory alloys are first summarized, then some possible alternative sealing methods discussed, and, finally, results from an initial proof-of-concept experiment described.

Koski, J.A.; Bronowski, D.R.

1997-11-01T23:59:59.000Z

187

Legal aspects of the maritime transport of radioactive materials its regulation in Mexico  

E-Print Network (OSTI)

This work has the object to analyse the International as much as National legal frameworks, the scopes and limits of the instruments which form it as well as the congruous that exist between them and the situation which actually prevails in the maritime transport field of radioactive materials in worldwide level and in Mexico taking into account the technical advances, the operational experience and radiological protection principles. In the chapter 1, the background on the uses of nuclear energy are described and its development by more of fifty years. The chapter 2 analyses about the establishment of nuclear technologies in Mexico as well as their evolution in medicine, agriculture, research and electric power generation areas. In chapter 3 it was analysed the role what the International Organizations have been playing for the establish of an International legal framework in the maritime transport of radioactive materials field. In the chapter 4, the International legal framework was analysed which is appli...

Aguilar, S

2001-01-01T23:59:59.000Z

188

Behavior of radioactive species during water injection into alloy breeder material  

Science Conference Proceedings (OSTI)

A fusion safety experiment was conducted to determine the consequences of water injection into lead-lithium alloy under postulated reactor accident conditions. The fraction of water reacted, quantity of hydrogen produced, and behavior of radioactive species associated with the use of this alloy as a breeder material were determined. The reaction products were identified, and the aerosol was characterized for particle size, chemical composition, and deposition rate. 2 refs., 3 figs., 7 tabs.

Jeppson, D.W.; Serinni, G. (Westinghouse Hanford Co., Richland, WA (USA); Commission of the European Communities, Ispra (Italy))

1989-09-01T23:59:59.000Z

189

Recommended Procedures for Measuring Radon Fluxes from Disposal Sites of Residual Radioactive Materials  

Science Conference Proceedings (OSTI)

This report recornmenrls instrumentation and methods suitable for measuring radon fluxes emanating from covered disposal sites of residual radioactive materials such as uranium mill tailings. Problems of spatial and temporal variations in radon flux are discussed and the advantages and disadvantages of several instruments are examined. A year-long measurement program and a two rnonth measurement rnethodology are then presented based on the inherent difficulties of measuring average radon flux over a cover using the recommended instrumentation.

Young,, J. A.; Thomas, V. W.; Jackson, P. 0.

1983-03-01T23:59:59.000Z

190

Apparatus for the processing of solid mixed waste containing radioactive and hazardous materials  

DOE Patents (OSTI)

Apparatus for the continuous heating and melting of a solid mixed waste bearing radioactive and hazardous materials to form separate metallic, slag and gaseous phases for producing compact forms of the waste material to facilitate disposal includes a copper split water-cooled (cold) crucible as a reaction vessel for receiving the waste material. The waste material is heated by means of the combination oaf plasma torch directed into the open upper portion of the cold crucible and an electromagnetic flux produced by induction coils disposed about the crucible which is transparent to electromagnetic fields. A metallic phase of the waste material is formed in a lower portion of the crucible and is removed in the form of a compact ingot suitable for recycling and further processing. A glass-like, non-metallic slag phase containing radioactive elements is also formed in the crucible and flows out of the open upper portion of the crucible into a slag ingot mold for disposal. The decomposition products of the organic and toxic materials are incinerated and converted to environmentally safe gases in the melter.

Gotovchikov, Vitaly T. (Moscow, RU); Ivanov, Alexander V. (Moscow, RU); Filippov, Eugene A. (Moscow, RU)

1999-03-16T23:59:59.000Z

191

Apparatus for the processing of solid mixed waste containing radioactive and hazardous materials  

DOE Patents (OSTI)

Apparatus for the continuous heating and melting of a solid mixed waste bearing radioactive and hazardous materials to form separate metallic, slag and gaseous phases for producing compact forms of the waste material to facilitate disposal includes a copper split water-cooled (cold) crucible as a reaction vessel for receiving the waste material. The waste material is heated by means of the combination of a plasma torch directed into the open upper portion of the cold crucible and an electromagnetic flux produced by induction coils disposed about the crucible which is transparent to electromagnetic fields. A metallic phase of the waste material is formed in a lower portion of the crucible and is removed in the form of a compact ingot suitable for recycling and further processing. A glass-like, non-metallic slag phase containing radioactive elements is also formed in the crucible and flows out of the open upper portion of the crucible into a slag ingot mold for disposal. The decomposition products of the organic and toxic materials are incinerated and converted to environmentally safe gases in the melter. 6 figs.

Gotovchikov, V.T.; Ivanov, A.V.; Filippov, E.A.

1999-03-16T23:59:59.000Z

192

Real time method and computer system for identifying radioactive materials from HPGe gamma-ray spectroscopy  

DOE Patents (OSTI)

A real-time method and computer system for identifying radioactive materials which collects gamma count rates from a HPGe gamma-radiation detector to produce a high-resolution gamma-ray energy spectrum. A library of nuclear material definitions ("library definitions") is provided, with each uniquely associated with a nuclide or isotope material and each comprising at least one logic condition associated with a spectral parameter of a gamma-ray energy spectrum. The method determines whether the spectral parameters of said high-resolution gamma-ray energy spectrum satisfy all the logic conditions of any one of the library definitions, and subsequently uniquely identifies the material type as that nuclide or isotope material associated with the satisfied library definition. The method is iteratively repeated to update the spectrum and identification in real time.

Rowland, Mark S. (Alamo, CA); Howard, Douglas E. (Livermore, CA); Wong, James L. (Dublin, CA); Jessup, James L. (Tracy, CA); Bianchini, Greg M. (Livermore, CA); Miller, Wayne O. (Livermore, CA)

2007-10-23T23:59:59.000Z

193

Property Valuation and Radioactive Materials Transportation: A Legal, Economic and Public Perception Analysis  

Science Conference Proceedings (OSTI)

The shipment of transuranic (TRU) radioactive waste to the Waste Isolation Pilot Plant (WIPP) in New Mexico raised a serious socioeconomic issue - the potential devaluation of property values due to the transportation of TRU waste from generator sites to the disposal facility. In 1992, the New Mexico Supreme Court held in City of Santa Fe v. Komis that a loss in value from public perception of risk was compensable. This issue has become an extremely important one for the development of the Yucca Mountain repository in Nevada for disposal of spent nuclear fuel and high-level radioactive waste. Much research has been conducted about the potential impacts of transportation of spent fuel and radioactive waste. This paper examines the pertinent studies conducted since the Komis case. It examines how the public debate on radioactive materials transportation continues and is now focused on transportation of high-level waste and spent nuclear fuel to the proposed Yucca Mountain repository. Finally, the paper suggests a path forward DOE can take to address this issue.

Holm, J. A.; Thrower, A. W.; Widmayer, D. A.; Portner, W.

2003-02-26T23:59:59.000Z

194

disposition | OpenEI  

Open Energy Info (EERE)

disposition disposition Dataset Summary Description This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report (AEO2011). This dataset is table 11, and contains only the reference case. The dataset uses million barrels per day. The data is broken down into crude oil, other petroleum supply, other non petroleum supply and liquid fuel consumption. Source EIA Date Released April 26th, 2011 (3 years ago) Date Updated Unknown Keywords 2011 AEO disposition EIA liquid fuels Supply Data application/vnd.ms-excel icon AEO2011: Liquid Fuels Supply and Disposition- Reference Case (xls, 117 KiB) Quality Metrics Level of Review Peer Reviewed Comment Temporal and Spatial Coverage Frequency Annually Time Period 2008-2035

195

Mixed-layered bismuth-oxygen-iodine materials for capture and waste disposal of radioactive iodine  

DOE Patents (OSTI)

Materials and methods of synthesizing mixed-layered bismuth oxy-iodine materials, which can be synthesized in the presence of aqueous radioactive iodine species found in caustic solutions (e.g. NaOH or KOH). This technology provides a one-step process for both iodine sequestration and storage from nuclear fuel cycles. It results in materials that will be durable for repository conditions much like those found in Waste Isolation Pilot Plant (WIPP) and estimated for Yucca Mountain (YMP). By controlled reactant concentrations, optimized compositions of these mixed-layered bismuth oxy-iodine inorganic materials are produced that have both a high iodine weight percentage and a low solubility in groundwater environments.

Krumhansl, James L; Nenoff, Tina M

2013-02-26T23:59:59.000Z

196

Assessment of the Integrated Facility Disposition Project at Oak Ridge  

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

Assessment of the Integrated Facility Disposition Project at Oak Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM In December 2007, the Assistant Secretary for Environmental Management (EM-1) invited the DOE Program Secretarial Offices (PSOs) of Nuclear Energy (NE), Science (SC), and the National Nuclear Security Administration (NNSA) to propose facilities and legacy waste for transfer to Environmental Management (EM) for final disposition or deactivation and decommissioning (D&D). Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM

197

Assessment of the Integrated Facility Disposition Project at Oak Ridge  

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

the Integrated Facility Disposition Project at Oak the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM In December 2007, the Assistant Secretary for Environmental Management (EM-1) invited the DOE Program Secretarial Offices (PSOs) of Nuclear Energy (NE), Science (SC), and the National Nuclear Security Administration (NNSA) to propose facilities and legacy waste for transfer to Environmental Management (EM) for final disposition or deactivation and decommissioning (D&D). Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM

198

Plutonium Disposition Program | National Nuclear Security Administration  

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

Home > Media Room > Fact Sheets > Plutonium Disposition Program Home > Media Room > Fact Sheets > Plutonium Disposition Program Fact Sheet Plutonium Disposition Program Jun 26, 2013 SUPPORTING NUCLEAR NONPROLIFERATION Weapon-grade plutonium and highly enriched uranium (HEU) are the critical ingredients for making a nuclear weapon. With the end of the Cold War, hundreds of tons of these materials were determined to be surplus to U.S. and Russian defense needs. Denying access to plutonium and HEU is the best way to prevent nuclear proliferation to rogue states and terrorist organizations. The most certain method to prevent these materials from falling into the wrong hands is to dispose of them. During the April 2010 Nuclear Security Summit, Secretary of State Hillary Rodham Clinton and Russian Foreign Minister Sergey Lavrov signed a protocol

199

Alternatives for the disposal of NORM (naturally occurring radioactive materials) wastes in Texas  

SciTech Connect

Some of the Texas wastes containing naturally occurring radioactive materials (NORM) have been disposed of in a uranium mill tailings impoundment. There is currently no operating disposal facility in Texas to accept these wastes. As a result, some wastes containing extremely small amounts of radioactivity are sent to elaborate disposal sites at extremely high costs. The Texas Low-Level Radioactive Waste Disposal Authority has sponsored a study to investigate lower cost, alternative disposal methods for certain wastes containing small quantities of NORM. This paper presents the results of a multipathway safety analysis of various scenarios for disposing of wastes containing limited quantities of NORM in Texas. The wastes include pipe scales and sludges from oil and gas production, residues from rare-earth mineral processing, and water treatment resins, but exclude large-volume, diffuse wastes (coal fly ash, phosphogypsum). The purpose of the safety analysis is to define concentration and quantity limits for the key nuclides of NORM that will avoid dangerous radiation exposures under different waste disposal scenarios.

Nielson, K.K.; Rogers, V.C. (Rogers Associates Engineering Corporation, Salt Lake City, UT (USA)); Pollard, C.G. (Texas Low-Level Radioactive Waste Disposal Authority, Austin (USA))

1989-11-01T23:59:59.000Z

200

THE USE OF DIGITAL RADIOGRAPHY IN THE EVALUATION OF RADIOACTIVE MATERIALS PACKAGING PERFORMANCE TESTING  

Science Conference Proceedings (OSTI)

New designs of radioactive material shipping packages are required to be evaluated in accordance with 10 CFR Part 71, ''Packaging and Transportation of Radioactive Material''. This paper will discuss the use of digital radiography to evaluate the effects of the tests required by 10 CFR 71.71, Normal Conditions of Transport (NCT), and 10 CFR 71.73, Hypothetical Accident Conditions (HAC). One acceptable means of evaluating packaging performance is to subject packagings to the series of NCT and HAC tests. The evaluation includes a determination of the effect on the packaging by the conditions and tests. That determination has required that packagings be cut and sectioned to learn the actual effects on internal components. Digital radiography permits the examination of internal packaging components without sectioning a package. This allows a single package to be subjected to a series of tests. After each test, the package is digitally radiographed and the effects of particular tests evaluated. Radiography reduces the number of packages required for testing and also reduces labor and materials required to section and evaluate numerous packages. This paper will include a description of the digital radiography equipment used in the testing and evaluation of the 9977 and 9978 packages at SRNL. The equipment is capable of making a single radiograph of a full-sized package in one exposure. Radiographs will be compared to sectioned packages that show actual conditions compared to radiographic images.

May, C; Lawrence Gelder, L; Boyd Howard, B

2007-03-22T23:59:59.000Z

Note: This page contains sample records for the topic "disposition radioactive materials" 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

Critically safe vacuum pickup for use in wet or dry cleanup of radioactive materials  

DOE Patents (OSTI)

A vacuum pickup of critically safe quantity and geometric shape is used in cleanup of radioactive materials. Collected radioactive material is accumulated in four vertical, parallel, equally spaced canisters arranged in a cylinder configuration. Each canister contains a filter bag. An upper intake manifold includes four 90 degree spaced, downward facing nipples. Each nipple communicates with the top of a canister. The bottom of each canister communicates with an exhaust manifold comprising four radially extending tubes that meet at the bottom of a centrally located vertical cylinder. The top of the central cylinder terminates at a motor/fan power head. A removable HEPA filter is located intermediate the top of the central cylinder and the power head. Four horizontal bypass tubes connect the top of the central cylinder to the top of each of the canisters. Air enters the vacuum cleaner via a hose connected to the intake manifold. Air then travels down the canisters, where particulate material is accumulated in generally equal quantities in each filter bag. Four air paths of bag filtered air then pass radially inward to the bottom of the central cylinder. Air moves up the central cylinder, through the HEPA filter, through a vacuum fan compartment, and exits the vacuum cleaner. A float air flow valve is mounted at the top of the central cylinder. When liquid accumulates to a given level within the central cylinder, the four bypass tubes, and the four canisters, suction is terminated by operation of the float valve.

Zeren, Joseph D. (390 Forest Ave., Boulder, CO 80304)

1994-01-01T23:59:59.000Z

202

Radiological Dose Assessment Related to Management of Naturally Occurring Radioactive Materials Generated by the Petroleum Industry  

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

Tebes is affiliated with the University of Illinois. Tebes is affiliated with the University of Illinois. ANL/EAD-2 Radiological Dose Assessment Related to Management of Naturally Occurring Radioactive Materials Generated by the Petroleum Industry by K.P. Smith, D.L. Blunt, G.P. Williams, and C.L. Tebes * Environmental Assessment Division Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439 September 1996 Work sponsored by the United States Department of Energy, Office of Policy iii CONTENTS ACKNOWLEDGMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . vii NOTATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . viii ABSTRACT . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 SUMMARY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

203

Bibliography of reports, papers, and presentations on naturally occurring radioactive material (NORM) in petroleum industry wastes  

Science Conference Proceedings (OSTI)

This bibliography was created to support projects conducted by Argonne National Laboratory (ANL) addressing issues related to naturally occurring radioactive material (NORM) in petroleum industry wastes. The bibliography provides citations for many of the available published reports, papers, articles, and presentations on petroleum industry NORM. In the past few years, the rapid expansion of NORM treatment and disposal technologies, the efforts to characterize NORM wastes and their associated potential risks, and the promulgation of state-level NORM regulatory programs have been well-documented in project reports and in papers presented at technical conferences and symposia. There are 221 citations.

Smith, K.P.; Wilkey, M.L.; Hames, R.D.

1997-07-01T23:59:59.000Z

204

Request For Records Disposition | Department of Energy  

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

Strategic Petroleum Reserve Request For Records Disposition More Documents & Publications Request For Records Disposition Authority: Strategic Petroleum Reserve Project Management...

205

Hanford Tank Waste Retrieval, Treatment and Disposition Framework |  

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

Hanford Tank Waste Retrieval, Treatment and Disposition Framework Hanford Tank Waste Retrieval, Treatment and Disposition Framework Hanford Tank Waste Retrieval, Treatment and Disposition Framework Completing the Office of River Protection (ORP) mission of stabilizing 56 million gallons of chemical and radioactive waste stored in Hanford's 177 tanks is one of the Energy Department's highest priorities. This Framework document outlines a phased approach for beginning tank waste treatment while continuing to resolve technical issues with the Pretreatment and High-Level Waste Facilities. Hanford Tank Waste Retrieval, Treatment and Disposition Framework More Documents & Publications EIS-0391: Draft Environmental Impact Statement Waste Treatment Plant and Tank Farm Program EIS-0356: Notice of Intent to Prepare an Environmental Impact Statement

206

Hanford Tank Waste Retrieval, Treatment and Disposition Framework |  

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

Hanford Tank Waste Retrieval, Treatment and Disposition Framework Hanford Tank Waste Retrieval, Treatment and Disposition Framework Hanford Tank Waste Retrieval, Treatment and Disposition Framework Completing the Office of River Protection (ORP) mission of stabilizing 56 million gallons of chemical and radioactive waste stored in Hanford's 177 tanks is one of the Energy Department's highest priorities. This Framework document outlines a phased approach for beginning tank waste treatment while continuing to resolve technical issues with the Pretreatment and High-Level Waste Facilities. Hanford Tank Waste Retrieval, Treatment and Disposition Framework More Documents & Publications EIS-0391: Draft Environmental Impact Statement Waste Treatment Plant and Tank Farm Program EIS-0356: Notice of Intent to Prepare an Environmental Impact Statement

207

APPLICATION OF POLYURETHANE FOAM FOR IMPACT ABSORPTION AND THERMAL INSULATION FOR GENERAL PURPOSE RADIOACTIVE MATERIALS PACKAGINGS  

Science Conference Proceedings (OSTI)

Polyurethane foam has been employed in impact limiters for large radioactive materials packagings since the early 1980's. Its consistent crush response, controllable structural properties and excellent thermal insulating characteristics have made it attractive as replacement for the widely used cane fiberboard for smaller, drum size packagings. Accordingly, polyurethane foam was chosen for the overpack material for the 9977 and 9978 packagings. The study reported here was undertaken to provide data to support the analyses performed as part of the development of the 9977 and 9978, and compared property values reported in the literature with published property values and test results for foam specimens taken from a prototype 9977 packaging. The study confirmed that, polyurethane foam behaves in a predictable and consistent manner and fully satisfies the functional requirements for impact absorption and thermal insulation.

Smith, A; Glenn Abramczyk, G; Paul Blanton, P; Steve Bellamy, S; William Daugherty, W; Sharon Williamson, S

2009-02-18T23:59:59.000Z

208

THERMAL EVALUATION OF DRUM TYPE RADIOACTIVE MATERIAL PACKAGING ARRAYS IN STORAGE  

SciTech Connect

Drum type packages are routinely used to transport radioactive material (RAM) in the U.S. Department of Energy (DOE) complex. These packages are designed to meet the federal regulations described in 10 CFR 71.[1] In recent years, there has been a greater need to use these packagings to store the excess fissile material, especially plutonium for long term storage. While the design requirements for safe transportation of these packagings are well defined, the requirements for safe long term storage are not well established. Since the RAM contents in the packagings produce decay heat, it is important that they are stored carefully to prevent overheating of the containment vessel (CV) seals to prevent any leakage and the impact limiter to maintain the package structural integrity. This paper analyzes different storage arrays for a typical 9977 packaging for thermal considerations and makes recommendations for their safe storage under normal operating conditions.

Gupta, N

2009-04-27T23:59:59.000Z

209

Test methods for selection of materials of construction for high-level radioactive waste vitrification. Revision  

Science Conference Proceedings (OSTI)

Candidate materials of construction were evaluated for a facility at the Department of Energy's Savannah River Plant to vitrify high-level radioactive waste. Limited operating experience was available under the corrosive conditions of the complex vitrification process. The objective of the testing program was to provide a high degree of assurance that equipment will meet or exceed design lifetimes. To meet this objective in reasonable time and minimum cost, a program was designed consisting of a combination of coupon immersion and electrochemical laboratory tests and pilot-scale tests. Stainless steels and nickel-based alloys were tested. Alloys that were most resistant to general and local attack contained nickel, molybdenum (>9%), and chromium (where Cr + Mo > 30%). Alloy C-276 was selected as the reference material for process equipment. Stellite 6 was selected for abrasive service in the presence of formic acid. Alloy 690 and ALLCORR were selected for specific applications.

Bickford, D F; Corbett, R A; Morrison, W S

1986-01-01T23:59:59.000Z

210

Compendium of federal and state radioactive materials transportation laws and regulations: Transportation Legislative Database (TLDB)  

SciTech Connect

The Transportation Legislative Database (TLDB) is an on-line information service containing detailed information on legislation and regulations regarding the transportation of radioactive materials in the United States. The system is dedicated to serving the legislative and regulatory information needs of the US Department of Energy and other federal agencies; state, tribal, and local governments; the hazardous materials transportation industry; and interested members of the general public. In addition to the on-line information service, quarterly and annual Legal Developments Reports are produced using information from the TLDB. These reports summarize important changes in federal and state legislation, regulations, administrative agency rulings, and judicial decisions over the reporting period. Information on significant legal developments at the tribal and local levels is also included on an as-available basis. Battelle's Office of Transportation Systems and Planning (OTSP) will also perform customized searches of the TLDB and produce formatted printouts in response to specific information requests.

Not Available

1989-10-01T23:59:59.000Z

211

Derivation of guidelines for uranium residual radioactive material in soil at the New Brunswick Site, Middlesex County, New Jersey  

SciTech Connect

Residual radioactive material guidelines for uranium in soil were derived for the New Brunswick Site, located in Middlesex County, New Jersey. This site has been designated for remedial action under the Formerly Utilized Sites Remedial Action Program of the US Department of Energy (DOE). Residual radioactive material guidelines for individual radionuclides of concern and total uranium were derived on the basis of the requirement that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works in the immediate vicinity of the New Brunswick Site should not exceed a dose of 30 mrem/yr following remedial action for the current-use and likely future-use scenarios or a dose of 100 mrem/yr for less likely future-use scenarios. The DOE residual radioactive material guideline computer code, RESRAD, was used in this evaluation; RESRAD implements the methodology described in the DOE manual for establishing residual radioactive material guidelines. The guidelines derived in this report are intended to apply to the remediation of these remaining residual radioactive materials at the site. The primary radionuclides of concern in these remaining materials are expected to be radium-226 and, to a lesser extent, natural uranium and thorium. The DOE has established generic cleanup guidelines for radium and thorium in soil; however, cleanup guidelines for other radionuclides must be derived on a site-specific basis.

Dunning, D.; Kamboj, S.; Nimmagadda, M.; Yu, C. [Argonne National Lab., IL (United States). Environmental Assessment Div.

1996-02-01T23:59:59.000Z

212

In-situ remediation of naturally occurring radioactive materials with high-permeability hydraulic fracturing  

E-Print Network (OSTI)

This thesis addresses the problem of removal of Naturally Occurring Radioactive Materials, NORM, and describes an effective alternative to the current treatment method for their removal. High-pen-meability fracturing, recently established in the petroleum industry, is the recommended technique. NORM are found throughout subterranean formations. Whenever fluids from petroleum or water reservoirs are produced NORM are present in varying quantities. NORM can only be sensed with radiation detectors. However, they have proven carcinogens, and the US Environmental Protection Agency has set a limit on the maximum contaminated level of any stream. Until now, the preferred method of treatment was to remove NORM from contaminated waters with specially designed filters, which in turn create a new problem. The same filters that are used to treat the water themselves become highly radioactive with a considerable disposal problem. In the petroleum industry, NORM become concentrated in the scale that is deposited inside the well or surface pipes. When scale is removed, it can be so radioactive that it can only be stored in toxic sites. Additionally, as water is produced along with oil, so are NORM. Until now, for the Gulf of Mexico at least, produced water has been released into the ocean, but the Environmental Protection Agency (EPA) is threatening to change this. In the North Sea the regulations are already stricter. There is then a compelling motivation to remove NORM before they are produced, and thus, eliminate the disposal problem. A high-permeability fracture design is presented which modifies existing petroleum practices by introducing within the proppant pack highly selective radionuclide sorbents. These sorbents, at calculated concentrations, can remove NORM readily for several years from typical flow rates containing typical NORM concentrations.

Demarchos, Andronikos Stavros

1998-01-01T23:59:59.000Z

213

Instrumentation, Equipment and Methods for the In Vivo Measurement of Radioactive Material in the Body  

SciTech Connect

The current applications for the in vivo measurement of radioactive material can be divided into three broad categories: (1) occupational exposure monitoring, (2) monitoring of the public, and (3) medical monitoring. The focus of this chapter is on occupational exposure monitoring that is part of an internal dosimetry program for monitoring workers for intakes and assessing the dose consequences of an intake. In the 1920's when electroscopes were first used to measure radium in the body of dial painters issues affecting the measurement accuracy were identified related to external contamination interferences, properly measuring the instrument background, need for measurement QC, microphonic interferences, shielding and others. The sophistication of the radiation detection instrumentation has evolved to the point where most systems today employ one or more detectors primarily either sodium iodide or germanium. Many different styles of detectors and cryostat designs are used at different facilities. However, the same issues identified in the 1920's are still issues today. The in vivo measurement systems are calibrated with anthropometric phantoms that simulate the body or parts of the body. Whole body phantoms, torso phantoms, lung phantoms, thyroid phantoms and skeletal phantoms are just some of the different types used.The systems are typically shielded with low background materials such as pre-World War II steel from battleships. Interferences can come from naturally occurring radioactive material, medically administered radiopharmaceuticals, equipment instability, non-ionizing electromagnetic radiation and other sources. These contribute to the uncertainties in measurement results that can range from 10% to 1000% or more depending on the measurement system, the energy of the radiation associated with the radionuclide to be measured, the accuracy of the phantom versus the person especially how well the distributions of activity match.

Lynch, Timothy P.

2005-07-01T23:59:59.000Z

214

Estimates of fire environments in ship holds containing radioactive material packages  

SciTech Connect

Fire environments that occur on cargo ships differ significantly from the fire environments found in land transport. Cargo ships typically carry a large amount of flammable fuel for propulsion and shipboard power, and may transport large quantities of flammable cargo. As a result, sea mode transport accident records contain instances of long lasting and intense fires. Since Irradiated Nuclear Fuel (INF) casks are not carried on tankers with large flammable cargoes, most of these dramatic, long burning fires are not relevant threats, and transport studies must concentrate on those fires that are most likely to occur. By regulation, INF casks must be separated from flammable cargoes by a fire-resistant, liquid-tight partition. This makes a fire in an adjacent ship hold the most likely fire threat. The large size of a cargo ship relative to any spent nuclear fuel casks on board, however, may permit a severe, long lasting fire to occur with little or no thermal impact on the casks. Although some flammable materials such as shipping boxes or container floors may exist in the same hold with the cask, the amount of fuel available may not provide a significant threat to the massive transport casks used for radioactive materials. This shipboard fire situation differs significantly from the regulatory conditions specified in 10 CFR 71 for a fully engulfing pool fire. To learn more about the differences, a series of simple thermal analyses has been completed to estimate cask behavior in likely marine and land thermal accident situations. While the calculations are based on several conservative assumptions, and are only preliminary, they illustrate that casks are likely to heat much more slowly in shipboard hold fires than in an open pool fire. The calculations also reinforce the basic regulatory concept that for radioactive materials, the shipping cask, not the ship, is the primary protection barrier to consider.

Koski, J.A.; Cole, J.K.; Hohnstreiter, G.F. [Sandia National Labs., Albuquerque, NM (United States); Wix, S.D. [GRAM, Inc., Albuquerque, NM (United States)

1995-12-31T23:59:59.000Z

215

EIS-0283-S2: Surplus Plutonium Disposition Supplemental Environmental  

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

3-S2: Surplus Plutonium Disposition Supplemental 3-S2: Surplus Plutonium Disposition Supplemental Environmental Impact Statement EIS-0283-S2: Surplus Plutonium Disposition Supplemental Environmental Impact Statement Summary This EIS analyzes the potential environmental impacts associated with changes to the surplus plutonium disposition program, including changes to the inventory of surplus plutonium and proposed new alternatives. The original EIS is available here. For more information, see: www.nnsa.energy.gov/nepa/spdsupplementaleis Public Comment Opportunities None available at this time. Documents Available for Download April 25, 2013 EIS-0283-S2: Interim Action Determination Surplus Plutonium Disposition Supplemental Environmental Impact Statement (K-Area Materials Storage (KAMS) Area Expansion at the Savannah River Site)

216

Highly enriched uranium (HEU) storage and disposition program plan  

SciTech Connect

Recent changes in international relations and other changes in national priorities have profoundly affected the management of weapons-usable fissile materials within the United States (US). The nuclear weapon stockpile reductions agreed to by the US and Russia have reduced the national security requirements for these fissile materials. National policies outlined by the US President seek to prevent the accumulation of nuclear weapon stockpiles of plutonium (Pu) and HEU, and to ensure that these materials are subjected to the highest standards of safety, security and international accountability. The purpose of the Highly Enriched Uranium (HEU) Storage and Disposition Program Plan is to define and establish a planned approach for storage of all HEU and disposition of surplus HEU in support of the US Department of Energy (DOE) Fissile Material Disposition Program. Elements Of this Plan, which are specific to HEU storage and disposition, include program requirements, roles and responsibilities, program activities (action plans), milestone schedules, and deliverables.

Arms, W.M.; Everitt, D.A.; O`Dell, C.L.

1995-01-01T23:59:59.000Z

217

Toward the Framework and Implementation for Clearance of Materials from Regulated Facilities  

SciTech Connect

The disposition of solid materials from nuclear facilities has been a subject of public debate for several decades. The primary concern has been the potential health effects resulting from exposure to residual radioactive materials to be released for unrestricted use. These debates have intensified in the last decade as many regulated facilities are seeking viable management decisions on the disposition of the large amounts of materials potentially containing very low levels of residual radioactivity. Such facilities include the nuclear weapons complex sites managed by the U.S. Department of Energy (DOE), commercial power plants licensed by the U.S. Nuclear Regulatory Commission (NRC), and other materials licensees regulated by the NRC or the Agreement States. Other facilities that generate radioactive material containing naturally occurring radioactive materials (NORM) or technologically enhanced NORM (TENORM) are also seeking to dispose of similar materials that may be radioactively contaminated. In contrast to the facilities operated by the DOE and the nuclear power plants licensed by the NRC, NORM and TENORM facilities are regulated by the individual states. Current federal laws and regulations do not specify criteria for releasing these materials that may contain residual radioactivity of either man-made or natural origin from regulatory controls. In fact, the current regulatory scheme offers no explicit provision as to permit materials being released as ''non-radioactive'', including those that are essentially free of contamination. The only method used to date with limited success has been case-by-case evaluation and approval. In addition, there is a poorly defined and inconsistent regulatory framework for regulating NORM and TENORM. Some years ago, the International Atomic Energy Agency (IAEA) introduced the concept of clearance, that is, controlling releases of any such materials within the regulatory domain. This paper aims to clarify clearance as an important disposition option for solid materials, establish the framework and basis of release, and discuss resolutions regarding the implementation of such a disposition option.

Chen, Shih-Yew; Moeller, Dade W.; Dornsife, William P.; Meyer, H Robert; Lamastra, Anthony; Lubenau, Joel O.; Strom, Daniel J.; Yusko, James G.

2005-08-01T23:59:59.000Z

218

Manual for implementing residual radioactive material guidelines using RESRAD, Version 5.0  

Science Conference Proceedings (OSTI)

This manual presents information for implementing US Department of Energy (DOE) guidelines for residual radioactive material. It describes the analysis and models used to derive site-specific guidelines for allowable residual concentrations of radionuclides in soil and the design and use of the RESRAD computer code for calculating doses, risks, and guideline values. It also describes procedures for implementing DOE policy for reducing residual radioactivity to levels that are as low as reasonably achievable. Two new pathways, radon inhalation and soil ingestion, have been added to RESRAD. Twenty-seven new radionuclides have also been added, and the cutoff half-life for associated radionuclides has been reduced to six months. Other major improvements to the RESRAD code include the ability to run sensitivity analyses, the addition of graphical output, user-specified dose factors, updated databases, an improved groundwater transport model, optional input of a groundwater concentration and a solubility constant, special models for tritium and carbon-14, calculation of cancer incidence risk, and the use of a mouse with menus.

Yu, C.; Zielen, A.J.; Cheng, J.J. [and others

1993-09-01T23:59:59.000Z

219

Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers  

Science Conference Proceedings (OSTI)

Three copper-based alloys and three iron- to nickel-based austenitic alloys are being considered as possible materials for fabrication of containers for disposal of high-level radioactive waste. This waste will include spent fuel assemblies from reactors as well as high-level waste in borosilicate glass and will be sent to the prospective site at Yucca Mountain, Nevada, for disposal. The containers must maintain substantially complete containment for at least 300 yr and perhaps as long as 1000 yr. During the first 50 yr after emplacement, they must be retrievable from the disposal site. Shortly after the containers are emplaced in the repository, they will be exposed to high temperatures and high gamma radiation fields from the decay of the high-level waste. This volume surveys the available data on oxidation and corrosion of the iron- to nickel-based austenitic materials (Types 304L and 316L stainless steels and Alloy 825) and the copper-based alloy materials (CDA 102 (oxygen-free copper), CDA 613 (Cu-7Al), and CDA 715 (Cu-30Ni)), which are the present candidates for fabrication of the containers. Studies that provided a large amount of data are highlighted, and those areas in which little data exists are identified. Examples of successful applications of these materials are given. On the basis of resistance to oxidation and general corrosion, the austenitic materials are ranked as follows: Alloy 825 (best), Type 316L stainless steel, and then Type 304L stainless steel (worst). For the copper-based materials, the ranking is as follows: CDA 715 and CDA 613 (both best), and CDA 102 (worst). 110 refs., 30 figs., 13 tabs.

Gdowski, G.E.; Bullen, D.B. (Science and Engineering Associates, Inc., Pleasanton, CA (USA))

1988-08-01T23:59:59.000Z

220

INVESTIGATION OF THE PRESENCE OF DRUGSTORE BEETLES WITHIN CELOTEX ASSEMBLIES IN RADIOACTIVE MATERIAL PACKAGINGS  

Science Conference Proceedings (OSTI)

During normal operations at the Department of Energy's Hanford Site in Hanford, WA, drugstore beetles, (Stegobium paniceum (L.) Coleoptera: Anobiidae), were found within the fiberboard subassemblies of two 9975 Shipping Packages. Initial indications were that the beetles were feeding on the Celotex{trademark} assemblies within the package. Celotex{trademark} fiberboard is used in numerous radioactive material packages serving as both a thermal insulator and an impact absorber for both normal conditions of transport and hypothetical accident conditions. The Department of Energy's Packaging Certification Program (EM-63) directed a thorough investigation to determine if the drugstore beetles were causing damage that would be detrimental to the safety performance of the Celotex{trademark}. The Savannah River National Laboratory is conducting the investigation with entomological expertise provided by Clemson University. The two empty 9975 shipping packages were transferred to the Savannah River National Laboratory in the fall of 2007. This paper will provide details and results of the ongoing investigation.

Loftin, B; Glenn Abramczyk, G

2008-06-04T23:59:59.000Z

Note: This page contains sample records for the topic "disposition radioactive materials" 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

Balancing health effects and economics in the management of radioactive materials  

SciTech Connect

The public perception of the benefits offered by nuclear energy and the risks to health and safety from ionizing radiation has dramatically altered over the fifty years since the advent of nuclear fission. The {open_quotes}Atomic Age{close_quotes} is seldom mentioned anymore. The attitudinal change from the acceptance of nuclear energy as an essential component of national defense, {open_quotes}Atoms for Peace,{close_quotes} and a new, abundant, and clean energy source for mankind to the perception of it as an object of protest and fear has resulted from events that included nuclear fallout from atmospheric weapons testing, Three Mile Island, Chernobyl, classified radiation experiments, and a generally hostile news media. As a reflection of public concerns over radiation, federal, state, and local regulations have greatly multiplied in both the types of radioactive materials addressed and the threshold activity levels at which these regulations become effective.

Sandquist, G.M.; Slaughter, D.M.; Rogers, V.C.

1994-12-31T23:59:59.000Z

222

Regulatory analysis on criteria for the release of patients administered radioactive material  

SciTech Connect

The Nuclear Regulatory Commission (NRC) has received two petitions to amend its regulations in 10 CFR Parts 20 and 35 as they apply to doses received by members of the public exposed to patients released from a hospital after they have been administered radioactive material. While the two petitions are not identical they both request that the NRC establish a dose limit of 5 millisieverts (0.5 rem) per year for individuals exposed to patients who have been administered radioactive materials. This Regulatory Analysis evaluates three alternatives. Alternative 1 is for the NRC to amend its patient release criteria in 10 CFR 35.75 to use the more stringent dose limit of 1 millisievert per year in 10 CFR 20.1301(a) for its patient release criteria. Alternative 2 is for the NRC to continue using the existing patient release criteria in 10 CFR 35.75 of 1,110 megabecquerels of activity or a dose rate at one meter from the patient of 0.05 millisievert per hour. Alternative 3 is for the NRC to amend the patient release criteria in 10 CFR 35.75 to specify a dose limit of 5 millisieverts for patient release. The evaluation indicates that Alternative 1 would cause a prohibitively large increase in the national health care cost from retaining patients in a hospital longer and would cause significant personal and psychological costs to patients and their families. The choice of Alternatives 2 or 3 would affect only thyroid cancer patients treated with iodine-131. For those patients, Alternative 3 would result in less hospitalization than Alternative 2. Alternative 3 has a potential decrease in national health care cost of $30,000,000 per year but would increase the potential collective dose from released therapy patients by about 2,700 person-rem per year, mainly to family members.

Schneider, S.; McGuire, S.A. [Nuclear Regulatory Commission, Washington, DC (United States). Div. of Regulatory Applications; Behling, U.H.; Behling, K.; Goldin, D. [Cohen (S.) and Associates, Inc., McLean, VA (United States)

1994-05-01T23:59:59.000Z

223

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

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

FOR RECORDS DISPOSITION AUTHORITY REQUEST FOR RECORDS DISPOSITION AUTHORITY Atomic Energy Commission REQUEST FOR RECORDS DISPOSITION AUTHORITY More Documents & Publications...

224

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

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

RECORDS DISPOSITION AUTHORITY More Documents & Publications Disposition Schedule: Human Radiation Experiments REQUEST FOR RECORDS DISPOSITION AUTHORITY REQUEST FOR RECORDS...

225

APPLICATION OF POLYURETHANE FOAM FOR IMPACT ABSORPTION AND THERMAL INSULATION FOR RADIOACTIVE MATERIALS PACKAGINGS.  

Science Conference Proceedings (OSTI)

Polyurethane foam has been widely used as an impact absorbing and thermal insulating material for large radioactive materials packages, since the 1980's. With the adoption of the regulatory crush test requirement, for smaller packages, polyurethane foam has been adopted as a replacement for cane fiberboard, because of its ability to withstand the crush test. Polyurethane foam is an engineered material whose composition is much more closely controlled than that of cane fiberboard. In addition, the properties of the foam can be controlled by controlling the density of the foam. The conditions under which the foam is formed, whether confined or unconfined have an affect on foam properties. The study reported here reviewed the application of polyurethane foam in RAM packagings and compared property values reported in the literature with published property values and test results for foam specimens taken from a prototype 9977 packaging. The study confirmed that, polyurethane foam behaves in a predictable and consistent manner and fully satisfies the functional requirements for impact absorption and thermal insulation.

Smith, A; Glenn Abramczyk, G; Paul Blanton, P; Steve Bellamy, S; William Daugherty, W; Sharon Williamson, S

2007-05-15T23:59:59.000Z

226

History of the US weapons-usable plutonium disposition program leading to DOE`s record of decision  

SciTech Connect

This report highlights important events and studies concerning surplus weapons-usable plutonium disposition in the United States. Included are major events that led to the creation of the U.S. Department of Energy (DOE) Office of Fissile Materials Disposition in 1994 and to that DOE office issuing the January 1997 Record of Decision for the Storage and Disposition of Weapons-Useable Fissile Materials Final Programmatic Environmental Impact Statement. Emphasis has been given to reactor-based plutonium disposition alternatives.

Spellman, D.J.; Thomas, J.F.; Bugos, R.G.

1997-04-01T23:59:59.000Z

227

IMPACT OF TARGET MATERIAL ACTIVATION ON PERSONNEL EXPOSURE AND RADIOACTIVE CONTAMINATION IN THE NATIONAL IGNITION FACILITY  

Science Conference Proceedings (OSTI)

Detailed activation analyses are performed for the different materials under consideration for use in the target capsules and hohlraums used during the ignition campaign on the National Ignition Facility. Results of the target material activation were additionally used to estimate the levels of contamination within the NIF target chamber and the workplace controls necessary for safe operation. The analysis examined the impact of using Be-Cu and Ge-doped CH capsules on the external dose received by workers during maintenance activities. Five days following a 20 MJ shot, dose rates inside the Target Chamber (TC) due to the two proposed capsule materials are small ({approx} 1 {micro}rem/h). Gold and depleted-uranium (DU) are considered as potential hohlraum materials. Following a shot, gold will most probably get deposited on the TC first wall. On the other hand, while noble-gas precursors from the DU are expected to stay in the TC, most of the noble gases are pumped out of the chamber and end up on the cryopumps. The dose rates inside the TC due to activated gold or DU, at 5 days following a 20 MJ shot, are about 1 mrem/h. Dose rates in the vicinity of the cryo-pumps (containing noble 'fission' gases) drop-off to about 1 mrem/h during the first 12 hours following the shot. Contamination from activation of NIF targets will result in the NIF target chamber exceeding DOE surface contamination limits. Objects removed from the TC will need to be managed as radioactive material. However, the results suggest that airborne contamination from resuspension of surface contamination will not be significant and is at levels that can be managed by negative ventilation when accessing the TC attachments.

Khater, H; Epperson, P; Thacker, R; Beale, R; Kohut, T; Brereton, S

2009-06-30T23:59:59.000Z

228

Survey of degradation modes of candidate materials for high-level radioactive-waste disposal containers  

Science Conference Proceedings (OSTI)

Three copper-based alloys and three iron- to nickel-based austenitic alloys are being considered as possible materials for fabrication of high-level radioactive-waste disposal containers. The waste will include spent fuel assemblies from reactors as well as high-level waste in borosilicate glass and will be sent to the prospective site at Yucca Mountain, Nevada, for disposal. The copper-based alloy materials are CDA 102 (oxygen-free copper), CDA 613 (Cu-7Al), and CDA 715 (Cu-30Ni). The austenitic materials are Types 304L and 316L stainless steels and Alloy 825. The waste-package containers must maintain substantially complete containment for at least 300 yr and perhaps as long as 1000 yr, and they must be retrievable from the disposal site during the first 50 yr after emplacement. The containers will be exposed to high temperatures and high gamma radiation fields from the decay of high-level waste. This volume surveys the available data on the phase stability of both groups of candidate alloys. The austenitic alloys are reviewed in terms of the physical metallurgy of the iron-chromium-nickel system, martensite transformations, carbide formation, and intermetallic-phase precipitation. The copper-based alloys are reviewed in terms of their phase equilibria and the possibility of precipitation of the minor alloying constituents. For the austenitic materials, the ranking based on phase stability is: Alloy 825 (best), Type 316L stainless steel, and then Type 304L stainless steel (worst). For the copper-based materials, the ranking is: CDA 102 (oxygen-free copper) (best), and then both CDA 715 and CDA 613. 75 refs., 24 figs., 6 tabs.

Bullen, D.B.; Gdowski, G.E. (Science and Engineering Associates, Inc., Pleasanton, CA (USA))

1988-08-01T23:59:59.000Z

229

Used Fuel Disposition R&D Documents | Department of Energy  

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

Technologies Used Fuel Disposition Research & Development Used Fuel Disposition R&D Documents Used Fuel Disposition R&D Documents April 30, 2012 Office of UNF Disposition...

230

DEVELOPMENT OF A NEW TYPE A(F)RADIOACTIVE MATERIAL PACKAGING FOR THE DEPARTMENT OF ENERGY  

SciTech Connect

In a coordinated effort, the Department of Transportation (DOT) and Nuclear Regulatory Commission (NRC) proposed the elimination of the Specification Packaging from 49 CFR 173.[1] In accordance with the Federal Register, issued on October 1, 2004, new fabrication of Specification Packages would no longer be authorized. In accordance with the NRC final rulemaking published January 26, 2004, Specification Packagings are mandated by law to be removed from service no later than October 1, 2008. This coordinated effort and resulting rulemaking initiated a planned phase out of Specification Type B and Type A fissile (F) material transportation packages within the Department of Energy (DOE) and its subcontractors. One of the Specification Packages affected by this regulatory change is the UN1A2 Specification Package, per DOT 49 CFR 173.417(a)(6). To maintain continuing shipments of DOE materials currently transported in UN1A2 Specification Package after the existing authorization expires, a replacement Type A(F) material packaging design is under development by the Savannah River National Laboratory. This paper presents a summary of the prototype design effort and testing of the new Type A(F) Package development for the DOE. This paper discusses the progress made in the development of a Type A Fissile Packaging to replace the expiring 49 CFR UN1A2 Specification Fissile Package. The Specification Package was mostly a single-use waste disposal container. The design requirements and authorized radioactive material contents of the UN1A2 Specification Package were defined in 49 CFR. A UN1A2 Specification Package was authorized to ship up to 350 grams of U-235 in any enrichment and in any non-pyrophoric form. The design was specified as a 55-gallon 1A2 drum overpack with a body constructed from 18 gauge steel with a 16 gauge drum lid. Drum closure was specified as a standard 12-gauge ring closure. The inner product container size was not specified but was listed as any container that met Specification 7A requirements per 49 CFR 178.350. Specification 7A containers were required to withstand Type A packaging tests required by 49CFR173.465 with compliance demonstrated through testing, analysis or similarity to other containers. The maximum weight of the 7A product container, the radioactive content, and any internal packaging was limited to 200 lbs. The total gross weight for the UN1A2 Specification Package was limited to 350 lbs. No additional restrictions were applied. Authorization for use did not require the UN1A2 Specification Package to be tested to the Normal Conditions of Transport (NCT) and Hypothetical Accident Conditions (HAC) required for performance based, Type A(F) packages certified by the NRC or DOE. The Type A(F) Packaging design discussed in this paper is required to be in compliance with the regulatory safety requirements defined in Code of Federal Regulations (CFR) 10 CFR 71.41 through 71.47 and 10 CFR71.71. Sub-criticality of content must be maintained under the Hypothetical Accident Conditions specified under 10 CFR71.73. These federal regulations, and other applicable DOE Orders and Guides, govern design requirements for a Type A(F) package. Type A(F) packages with less than an A2 quantity of radioactive material are not required to have a leak testable boundary. With this exception a Type A(F) package design is subject to the same test requirements set forth for the design of a performance based Type B packaging.

Blanton, P.; Eberl, K.

2008-09-14T23:59:59.000Z

231

Major Risk Factors to the Integrated Facility Disposition Project  

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

Oak Ridge Reservation Tennessee Major Risk Factors to the Integrated Facility Disposition Project (IFDP) Challenge The scope of the Integrated Facility Disposition Project (IFDP) needs to comprehensively address a wide range of environmental management risks at the Oak Ridge Reservation (ORO). These include: environmental remediation, regulatory compliance, deactivation and decommissioning (D&D) activities, and disposition of legacy materials and waste, along with the ongoing modernization, reindustrialization, and reconfiguration initiatives at the Oak Ridge National Laboratory and at the Y-12 National Security Complex. The balancing of the broad nature of these activities and issues at ORO are a key challenge for the IFDP especially since their interrelationship is not always obvious.

232

RADIATION HEAT TRANSFER ENVIRONMENT IN FIRE AND FURNACE TESTS OF RADIOACTIVE MATERIALS PAKCAGES  

SciTech Connect

The Hypothetical Accident Conditions (HAC) sequential test of radioactive materials packages includes a thermal test to confirm the ability of the package to withstand a transportation fire event. The test specified by the regulations (10 CFR 71) consists of a 30 minute, all engulfing, hydrocarbon fuel fire, with an average flame temperature of at least 800 C. The requirements specify an average emissivity for the fire of at least 0.9, which implies an essentially black radiation environment. Alternate test which provide equivalent total heat input at the 800 C time averaged environmental temperature may also be employed. When alternate tests methods are employed, such as furnace or gaseous fuel fires, the equivalence of the radiation environment may require justification. The effects of furnace and open confinement fire environments are compared with the regulatory fire environment, including the effects of gases resulting from decomposition of package overpack materials. The results indicate that furnace tests can produce the required radiation heat transfer environment, i.e., equivalent to the postulated pool fire. An open enclosure, with transparent (low emissivity) fire does not produce an equivalent radiation environment.

Smith, A

2008-12-31T23:59:59.000Z

233

Regulatory Initiatives for Control and Release of Technologically Enhanced Naturally-Occurring Radioactive Materials  

Science Conference Proceedings (OSTI)

Current drafts of proposed standards and suggested State regulations for control and release of technologically-enhanced naturally-occurring radioactive material (TENORM), and standards for release of volumetrically-contaminated material in the US are reviewed. These are compared to the recommendations of the International Atomic Energy Association (IAEA) Safety Series and the European Commission (EC) proposals. Past regulatory efforts with respect to TENORM in the US dealt primarily with oil-field related wastes. Currently, nine states (AK, GA, LA, MS, NM, OH, OR SC, TX) have specific regulations pertaining to TENORM, mostly based on uranium mill tailings cleanup criteria. The new US proposals are dose- or risk-based, as are the IAEA and EC recommendations, and are grounded in the linear no threshold hypothesis (LNT). TENORM wastes involve extremely large volumes, particularly scrap metal and mine wastes. Costs to control and dispose of these wastes can be considerable. The current debate over the validity of LNT at low doses and low dose rates is particularly germane to this discussion. Most standards setting organizations and regulatory agencies base their recommendations on the LNT. The US Environmental Protection Agency has released a draft Federal Guidance Report that recommends calculating health risks from low-level exposure to radionuclides based on the LNT. However, some scientific and professional organizations are openly questioning the validity of LNT and its basis for regulations, practices, and costs to society in general. It is not clear at this time how a non-linear regulatory scheme would be implemented.

Egidi, P.V.

1999-03-02T23:59:59.000Z

234

Facility Disposition Safety Strategy RM  

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

The Facility Disposition Safety Strategy (FDSS) Review Module is a tool that assists DOE federal project review teams in evaluating the adequacy of the facility documentation, preparations or...

235

Programmatic Environmental Assessment for the U. S. Department of Energy, Oak Ridge Operations Implementation of a Comprehensive Management Program for the Storage, Transportation, and Disposition of Potentially Reusable Uranium Materials  

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

IMPMZT IMPMZT PROGR4MMATIC ENVIRONMENTAL ASSESSME?X FOR THE U.S. DEPARTMENT OF ENERGY, OAK RIDGE OPER4TIOSS IMPLEMENTATION OF A COMPREHENSIVE MANAGEMEKT PROGK4hl FOR THE STORAGE, TRANSPORTATION, AND DISPOSITION OF POTENTIALLY REUSABLE URANJUh4 MATERIALS AGEhCY: U.S. DEPARTMENT OF ENERGY (DOE) ACTION: FINDI?iG OF NO SIGNIFICANT 1~IPAC-I SUMI\!L4RY: The U. S. DOE has completed a Programmatic Environmental Assessment (PE:,4) (DOE/E?,- 1393), which is incorporated herein by this reference. Tile purpose of the PEA is in assess potential enJ?ronmental impacts of the implementation of a comprehek-e management program for potentiaIly reusable ICW enriched uranium (LEU). norr,:al uranium (NU), and depleted uranium (DU). --l?prosimately 14,200 MTU (h?etric Tons of Uranium) of potentially reusable uranium is located at 15s

236

Disposition of Surplus Highly Enriched Uranium  

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

. . ------- .--- --. ---- DOE/EIS-0240 I United States Department of Energy I For Further Information Contact: U.S. Department of Energy Otice of Fissile Materials Disposition, 1000 Independence Ave., SW, Washington, D.C. 20585 1 I ---- I I . I I I I This report has been reproduced directly from the best available copy. Available to DOE and DOE contractors from the Office of Scientific and Technical Information, P.O. Box 62, Oak Ridge, TN 37831; telephone (423) 576-8401 for prices. Available to the public from the National Technical Information Service, 5285 Port Royal Road, Springfield, VA 22161. Copies of this document are available (while supplies last) upon written request to: I Office of Fissile Materials Disposition, MD-4 Forrestal Building United States Department of Energy 1000 Independence Avenue, SW Washington, DC 20585 , @ Printed with soy ink on recycled paper. -_. - COVERS~ET

237

Disposition of Surplus Highly Enriched Uranium  

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

EIS-0240-S EIS-0240-S For Further Information Contact: U.S. Departmel>t of Energy Office of Fissile Materials Disposition, 1000 Independence Ave., SW, Washington, D.C. 20585 . This report has been reproduced directly from the best available copy. Available to DOE and DOE contractors from the Office of Scientific and Technical Information, P.O. Box 62, Oak Ridge, TN 37831; telephone (423) 576-8401 for prices, Available to the public from the National Technical Information Service, 5285 Port Royal Road, Springfield, VA 22161. Copies of this document are available (while supplies last) upon written request to: Office of Fissile Materials Disposition, MD-4 Forrestal Building United States Department of Energy 1000 Independence Avenue, SW Washington, DC 20585 @ Printed with soy ink on recycled paper. .__- -. @ .: Depafimmt of Energy . i i~t " Wastin@on, DC 20585 June 1996 Dear hterested

238

Plutonium Disposition Now!  

SciTech Connect

A means for use of existing processing facilities and reactors for plutonium disposition is described which requires a minimum capital investment and allows rapid implementation. The scenario includes interim storage and processing under IAEA control, and fabrication into MOX fuel in existing or planned facilities in Europe for use in operating reactors in the two home countries. Conceptual studies indicate that existing Westinghouse four-loop designs can safety dispose of 0.94 MT of plutonium per calendar year. Thus, it would be possible to consume the expected US excess stockpile of about 50 MT in two to three units of this type, and it is highly likely that a comparable amount of the FSU excess plutonium could be deposed of in a few VVER-1000`s. The only major capital project for this mode of plutonium disposition would be the weapons-grade plutonium processing which could be done in a dedicated international facility or using existing facilities in the US and FSU under IAEA control. This option offers the potential for quick implementation at a very low cost to the governments of the two countries.

Buckner, M.R.

1995-05-24T23:59:59.000Z

239

IMPROVING THERMAL PERFORMANCE OF RADIOACTIVE MATERIAL DRUM TYPEPACKAGES BY USING HEAT PIPES  

Science Conference Proceedings (OSTI)

This paper presents a feasibility study to improve thermal loading of existing radioactive material packages by using heat pipes. The concept could be used to channel heat in certain directions and dissipate to the environment. The concept is applied to a drum type package because the drum type packages are stored and transported in an upright position. This orientation is suitable for heat pipe operation that could facilitate the heat pipe implementation in the existing well proven package designs or in new designs where thermal loading is high. In this position, heat pipes utilize gravity very effectively to enhance heat flow in the upward direction Heat pipes have extremely high effective thermal conductivity that is several magnitudes higher than the most heat conducting metals. In addition, heat pipes are highly unidirectional so that the effective conductivity for heat transfer in the reverse direction is greatly reduced. The concept is applied to the 9977 package that is currently going through the DOE certification review. The paper presents computer simulations using typical off-the-shelf heat pipe available configurations and performance data for the 9977 package. A path forward is outlined for implementing the concepts for further study and prototype testing.

Gupta, N

2007-03-06T23:59:59.000Z

240

Dismantlement and Disposition | National Nuclear Security Administrati...  

National Nuclear Security Administration (NNSA)

Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Dismantlement and Disposition Home > Our Mission > Managing the Stockpile > Dismantlement and Disposition Dismantlement...

Note: This page contains sample records for the topic "disposition radioactive materials" 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

CHARACTERIZATION OF SURPLUS PLUTONIUM FOR DISPOSITION OPTIONS  

SciTech Connect

The United States (U.S.) has identified 61.5 metric tons (MT) of plutonium that is permanently excess to use in nuclear weapons programs, including 47.2 MT of weapons-grade plutonium. Except for materials that remain in use for programs outside of national defense, including programs for nuclear-energy development, the surplus inventories will be stored safely by the Department of Energy (DOE) and then transferred to facilities that will prepare the plutonium for permanent disposition. Some items will be disposed as transuranic waste, low-level waste, or spent fuel. The remaining surplus plutonium will be managed through: (1) the Mixed Oxide (MOX) Fuel Fabrication Facility (FFF), to be constructed at the Savannah River Site (SRS), where the plutonium will be converted to fuel that will be irradiated in civilian power reactors and later disposed to a high-level waste (HLW) repository as spent fuel; (2) the SRS H-Area facilities, by dissolving and transfer to HLW systems, also for disposal to the repository; or (3) alternative immobilization techniques that would provide durable and secure disposal. From the beginning of the U.S. program for surplus plutonium disposition, DOE has sponsored research to characterize the surplus materials and to judge their suitability for planned disposition options. Because many of the items are stored without extensive analyses of their current chemical content, the characterization involves three interacting components: laboratory sample analysis, if available; non-destructive assay data; and rigorous evaluation of records for the processing history for items and inventory groups. This information is collected from subject-matter experts at inventory sites and from materials stabilization and surveillance programs, in cooperation with the design agencies for the disposition facilities. This report describes the operation and status of the characterization program.

Allender, J; Edwin Moore, E; Scott Davies, S

2008-07-15T23:59:59.000Z

242

Disposition of Surplus Highly Enriched Uranium  

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

@ @ Printed with soy ink on recycled paper. ,, ,, This report has been reproduced directly from the best available copy. Available to DOE and DOE contractors horn the Office of Scientific and Technical Information, P.O. Box 62, Oak Ridge, TN 37831; telephone (423) 576-8401 for prices, Available to the public from the National Technical Information Service, 5285 Port Royal Road, Springfield, VA 22161. Copies of this document are available (while supplies last) upon written request to: Office of Fissile Materials Disposition, MD-4 ' Forrestal Building United States Department of Energy 1000 Independence Avenue, SW Washington, DC 20585 Department of Energy Washington, DC 20585 June 1996 Dear hterested Party: The Disposition of Surplus Highly Enriched Uranium Final Environmental Impact Statemnt is enclosed for your information. This document has been prepared in accordance

243

Confidentiality and the Desire for Open Communication in the Transport of Radioactive Material to a National Repository  

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

Confidentiality, Security and Confidentiality, Security and Confidentiality, Security and Confidentiality, Security and the Desire for Open the Desire for Open Communication in the Communication in the Transport of Radioactive Transport of Radioactive Material to a National Material to a National Repository Repository A presentation to the A presentation to the DOE Transportation External Coordination (TEC) DOE Transportation External Coordination (TEC) Working Group Meeting Working Group Meeting Albuquerque, NM Albuquerque, NM 21 21 - - 23 April 2004 23 April 2004 Ronald B. Pope Consultant April 2004 April 2004 Confidentiality Confidentiality - - TEC Working TEC Working Group Group - - Albuquerque Albuquerque 2 2 Objectives Objectives Address and prompt TEC discussion on issues Address and prompt TEC discussion on issues

244

Method for making a low density polyethylene waste form for safe disposal of low level radioactive material  

DOE Patents (OSTI)

In the method of the invention low density polyethylene pellets are mixed in a predetermined ratio with radioactive particulate material, then the mixture is fed through a screw-type extruder that melts the low density polyethylene under a predetermined pressure and temperature to form a homogeneous matrix that is extruded and separated into solid monolithic waste forms. The solid waste forms are adapted to be safely handled, stored for a short time, and safely disposed of in approved depositories.

Colombo, P.; Kalb, P.D.

1984-06-05T23:59:59.000Z

245

Fate and transport processes controlling the migration of hazardous and radioactive materials from the Area 5 Radioactive Waste Management Site (RWMS)  

SciTech Connect

Desert vadose zones have been considered as suitable environments for the safe and long-term isolation of hazardous wastes. Low precipitation, high evapotranspiration and thick unsaturated alluvial deposits commonly found in deserts make them attractive as waste disposal sites. The fate and transport of any contaminant in the subsurface is ultimately determined by the operating retention and transformation processes in the system and the end result of the interactions among them. Retention (sorption) and transformation are the two major processes that affect the amount of a contaminant present and available for transport. Retention processes do not affect the total amount of a contaminant in the soil system, but rather decrease or eliminate the amount available for transport at a given point in time. Sorption reactions retard the contaminant migration. Permanent binding of solute by the sorbent is also possible. These processes and their interactions are controlled by the nature of the hazardous waste, the properties of the porous media and the geochemical and environmental conditions (temperature, moisture and vegetation). The present study summarizes the available data and investigates the fate and transport processes that govern the migration of contaminants from the Radioactive Waste Management Site (RWMS) in Area 5 of the Nevada Test Site (NTS). While the site is currently used only for low-level radioactive waste disposal, past practices have included burial of material now considered hazardous. Fundamentals of chemical and biological transformation processes are discussed subsequently, followed by a discussion of relevant results.

Estrella, R.

1994-10-01T23:59:59.000Z

246

A workshop on developing risk assessment methods for medical use of radioactive material. Volume 2: Supporting documents  

SciTech Connect

A workshop was held at the Idaho National Engineering Laboratory, August 16--18, 1994 on the topic of risk assessment on medical devices that use radioactive isotopes. Its purpose was to review past efforts to develop a risk assessment methodology to evaluate these devices, and to develop a program plan and a scoping document for future methodology development. This report contains presentation material and a transcript of the workshop. Participants included experts in the fields of radiation oncology, medical physics, risk assessment, human-error analysis, and human factors. Staff from the US Nuclear Regulatory Commission (NRC) associated with the regulation of medical uses of radioactive materials and with research into risk-assessment methods participated in the workshop. The workshop participants concurred in NRC`s intended use of risk assessment as an important technology in the development of regulations for the medical use of radioactive material and encouraged the NRC to proceed rapidly with a pilot study. Specific recommendations are included in the executive summary and the body of this report.

Tortorelli, J.P. [ed.] [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)

1995-08-01T23:59:59.000Z

247

Definition of Small Gram Quantity Contents for Type B Radioactive Material Transportation Packages: Activity-Based Content Limitations  

SciTech Connect

Since the 1960's, the Department of Transportation Specification (DOT Spec) 6M packages have been used extensively for transportation of Type B quantities of radioactive materials between Department of Energy (DOE) facilities, laboratories, and productions sites. However, due to the advancement of packaging technology, the aging of the 6M packages, and variability in the quality of the packages, the DOT implemented a phased elimination of the 6M specification packages (and other DOT Spec packages) in favor of packages certified to meet federal performance requirements. DOT issued the final rule in the Federal Register on October 1, 2004 requiring that use of the DOT Specification 6M be discontinued as of October 1, 2008. A main driver for the change was the fact that the 6M specification packagings were not supported by a Safety Analysis Report for Packaging (SARP) that was compliant with Title 10 of the Code of Federal Regulations part 71 (10 CFR 71). Therefore, materials that would have historically been shipped in 6M packages are being identified as contents in Type B (and sometimes Type A fissile) package applications and addenda that are to be certified under the requirements of 10 CFR 71. The requirements in 10 CFR 71 include that the Safety Analysis Report for Packaging (SARP) must identify the maximum radioactivity of radioactive constituents and maximum quantities of fissile constituents (10 CFR 71.33(b)(1) and 10 CFR 71.33(b)(2)), and that the application (i.e., SARP submittal or SARP addendum) demonstrates that the external dose rate (due to the maximum radioactivity of radioactive constituents and maximum quantities of fissile constituents) on the surface of the packaging (i.e., package and contents) not exceed 200 mrem/hr (10 CFR 71.35(a), 10 CFR 71.47(a)). It has been proposed that a 'Small Gram Quantity' of radioactive material be defined, such that, when loaded in a transportation package, the dose rates at external points of an unshielded packaging not exceed the regulatory limits prescribed by 10 CFR 71 for non-exclusive shipments. The mass of each radioisotope presented in this paper is limited by the radiation dose rate on the external surface of the package, which per the regulatory limit should not exceed 200 mrem/hr. The results presented are a compendium of allowable masses of a variety of different isotopes (with varying impurity levels of beryllium in some of the actinide isotopes) that, when loaded in an unshielded packaging, do not result in an external dose rate on the surface of the package that exceeds 190 mrem/hr (190 mrem/hr was chosen to provide 5% conservatism relative to the regulatory limit). These mass limits define the term 'Small Gram Quantity' (SGQ) contents in the context of radioactive material transportation packages. The term SGQ is isotope-specific and pertains to contents in radioactive material transportation packages that do not require shielding and still satisfy the external dose rate requirements. Since these calculated mass limits are for contents without shielding, they are conservative for packaging materials that provide some limited shielding or if the contents are placed into a shielded package. The isotopes presented in this paper were chosen as the isotopes that Department of Energy (DOE) sites most likely need to ship. Other more rarely shipped isotopes, along with industrial and medical isotopes, are planned to be included in subsequent extensions of this work.

Sitaraman, S; Kim, S; Biswas, D; Hafner, R; Anderson, B

2010-10-27T23:59:59.000Z

248

disposition. prices | OpenEI  

Open Energy Info (EERE)

disposition. prices disposition. prices Dataset Summary Description This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report (AEO2011). This dataset is Table 15, and contains only the reference case. The dataset uses gigawatts. The data is broken down into production, net imports, consumption by sector and price. Source EIA Date Released April 26th, 2011 (3 years ago) Date Updated Unknown Keywords 2011 AEO coal coal supply disposition. prices EIA Data application/vnd.ms-excel icon AEO2011: Coal Supply, Disposition, and Prices- Reference Case (xls, 91.7 KiB) Quality Metrics Level of Review Peer Reviewed Comment Temporal and Spatial Coverage Frequency Annually Time Period 2008-2035 License License Open Data Commons Public Domain Dedication and Licence (PDDL)

249

Unallocated Off-Specification Highly Enriched Uranium: Recommendations for Disposition  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy (DOE) has made significant progress with regard to disposition planning for 174 metric tons (MTU) of surplus Highly Enriched Uranium (HEU). Approximately 55 MTU of this 174 MTU are ''offspec'' HEU. (''Off-spec'' signifies that the isotopic or chemical content of the material does not meet the American Society for Testing and Materials standards for commercial nuclear reactor fuel.) Approximately 33 of the 55 MTU have been allocated to off-spec commercial reactor fuel per an Interagency Agreement between DOE and the Tennessee Valley Authority (1). To determine disposition plans for the remaining {approx}22 MTU, the DOE National Nuclear Security Administration (NNSA) Office of Fissile Materials Disposition (OFMD) and the DOE Office of Environmental Management (EM) co-sponsored this technical study. This paper represents a synopsis of the formal technical report (NNSA/NN-0014). The {approx} 22 MTU of off-spec HEU inventory in this study were divided into two main groupings: one grouping with plutonium (Pu) contamination and one grouping without plutonium. This study identified and evaluated 26 potential paths for the disposition of this HEU using proven decision analysis tools. This selection process resulted in recommended and alternative disposition paths for each group of HEU. The evaluation and selection of these paths considered criteria such as technical maturity, programmatic issues, cost, schedule, and environment, safety and health compliance. The primary recommendations from the analysis are comprised of 7 different disposition paths. The study recommendations will serve as a technical basis for subsequent programmatic decisions as disposition of this HEU moves into the implementation phase.

Bridges, D. N.; Boeke, S. G.; Tousley, D. R.; Bickford, W.; Goergen, C.; Williams, W.; Hassler, M.; Nelson, T.; Keck, R.; Arbital, J.

2002-02-27T23:59:59.000Z

250

Molten salt oxidation of mixed wastes: Separation of radioactive materials and Resource Conservation and Recovery Act (RCRA) materials  

Science Conference Proceedings (OSTI)

The Oak Ridge National Laboratory (ORNL) is involved in a program to apply a molten salt oxidation (MSO) process to the treatment of mixed wastes at Oak Ridge and other Department of Energy (DOE) sites. Mixed wastes are defined as those wastes that contain both radioactive components, which are regulated by the atomic energy legislation, and hazardous waste components, which are regulated under the Resource Conservation and Recovery Act (RCRA). A major part of our ORNL program involves the development of separation technologies that are necessary for the complete treatment of mixed wastes. The residues from the MSO treatment of the mixed wastes must be processed further to separate the radioactive components, to concentrate and recycle residues, or to convert the residues into forms acceptable for final disposal. This paper is a review of the MSO requirements for separation technologies, the information now available, and the concepts for our development studies.

Bell, J.T.; Haas, P.A.; Rudolph, J.C.

1993-12-01T23:59:59.000Z

251

Radioactivity in consumer products  

SciTech Connect

Papers presented at the conference dealt with regulations and standards; general and biological risks; radioluminous materials; mining, agricultural, and construction materials containing radioactivity; and various products containing radioactive sources.

Moghissi, A.A.; Paras, P.; Carter, M.W.; Barker, R.F. (eds.)

1978-08-01T23:59:59.000Z

252

Roadmapping the Resolution of Gas Generation Issues in Packages Containing Radioactive Waste/Materials - A Status Report  

DOE Green Energy (OSTI)

Gas generation issues, particularly hydrogen, have been an area of concern for the transport and storage of radioactive materials and waste in the Department of Energy (DOE) Complex. Potentially combustible gases can be generated through a variety of reactions, including chemical reactions and radiolytic decomposition of hydrogen-containing material. Since transportation regulations prohibit shipment of explosives and radioactive materials together, it was decided that hydrogen generation was a problem that warranted the execution of a high-level roadmapping effort. This paper discusses the major gas generation issues within the DOE Complex and the research that has been and is being conducted by the transuranic (TRU) waste, nuclear materials, and spent nuclear fuels (SNF) programs within DOE's Environmental Management (EM) organizations to address gas generation concerns. This paper presents a ''program level'' roadmap that links technology development to program needs and identifies the probability of success in an effort to understand the programmatic risk associated with the issue of gas generation. This paper also presents the status of the roadmap and follow-up activities.

Luke, D.E. (INEEL); Hamp, S. (DOE-Albuquerque Operations Office)

2002-01-04T23:59:59.000Z

253

Roadmapping the Resolution of Gas Generation Issues in Packages Containing Radioactive Waste/Materials - A Status Report  

SciTech Connect

Gas generation issues, particularly hydrogen, have been an area of concern for the transport and storage of radioactive materials and waste in the Department of Energy (DOE) Complex. Potentially combustible gases can be generated through a variety of reactions, including chemical reactions and radiolytic decomposition of hydrogen-containing material. Since transportation regulations prohibit shipment of explosives and radioactive materials together, it was decided that hydrogen generation was a problem that warranted the execution of a high-level roadmapping effort. This paper discusses the major gas generation issues within the DOE Complex and the research that has been and is being conducted by the transuranic (TRU) waste, nuclear materials, and spent nuclear fuels (SNF) programs within DOE's Environmental Management (EM) organizations to address gas generation concerns. This paper presents a ''program level'' roadmap that links technology development to program needs and identifies the probability of success in an effort to understand the programmatic risk associated with the issue of gas generation. This paper also presents the status of the roadmap and follow-up activities.

Luke, D.E. (INEEL); Hamp, S. (DOE-Albuquerque Operations Office)

2002-01-04T23:59:59.000Z

254

Roadmapping the Resolution of Gas Generation Issues in Packages Containing Radioactive Waste/Materials - A Status Report  

SciTech Connect

Gas generation issues, particularly hydrogen, have been an area of concern for the transport and storage of radioactive materials and waste in the Department of Energy (DOE) Complex. Potentially combustible gases can be generated through a variety of reactions, including chemical reactions and radiolytic decomposition of hydrogen- containing material. Since transportation regulations prohibit shipment of explosives and radioactive materials together, it was decided that hydrogen generation was a problem that warranted the execution of a high-level roadmapping effort. This paper discusses the major gas generation issues within the DOE Complex and the research that has been and is being conducted by the transuranic (TRU) waste, nuclear materials, and spent nuclear fuels (SNF) programs within DOEs Environmental Management (EM) organizations to address gas generation concerns. This paper presents a "program level" roadmap that links technology development to program needs and identifies the probability of success in an effort to understand the programmatic risk associated with the issue of gas generation. This paper also presents the status of the roadmap and follow-up activities.

Luke, Dale Elden; Hamp, S.

2002-02-01T23:59:59.000Z

255

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

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

REQUEST FOR RECORDS DISPOSITION AUTHORITY REQUEST FOR RECORDS DISPOSITION AUTHORITY U. S. Atomic Energy Commision REQUEST FOR RECORDS DISPOSITION AUTHORITY More Documents &...

256

Request For Records Disposition Authority | Department of Energy  

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

Oil and Gas Division Request For Records Disposition Authority More Documents & Publications REQUEST FOR RECORDS DISPOSITION AUTHORITY Request For Records Disposition Autnority...

257

Request For Records Disposition Authority | Department of Energy  

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

Disposition Authority Request For Records Disposition Authority Naval Petroleum and Oil Shale Reserves Request For Records Disposition Authority More Documents & Publications...

258

EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho  

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

EM Makes Significant Progress on Dispositioning Transuranic Waste EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site December 24, 2013 - 12:00pm Addthis Workers treat sludge-bearing, transuranic waste from the Advanced Mixed Waste Treatment Project. Workers treat sludge-bearing, transuranic waste from the Advanced Mixed Waste Treatment Project. A tank at the Materials and Fuels Complex containing residual sodium is moved prior to waste treatment. A tank at the Materials and Fuels Complex containing residual sodium is moved prior to waste treatment. Distillation equipment is shown prior to transport to the Idaho site. Distillation equipment is shown prior to transport to the Idaho site. In these 2010 photographs, unexploded ordnance were collected and then detonated onsite at the Mass Detonation Area.

259

EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho  

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

EM Makes Significant Progress on Dispositioning Transuranic Waste EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site December 24, 2013 - 12:00pm Addthis Workers treat sludge-bearing, transuranic waste from the Advanced Mixed Waste Treatment Project. Workers treat sludge-bearing, transuranic waste from the Advanced Mixed Waste Treatment Project. A tank at the Materials and Fuels Complex containing residual sodium is moved prior to waste treatment. A tank at the Materials and Fuels Complex containing residual sodium is moved prior to waste treatment. Distillation equipment is shown prior to transport to the Idaho site. Distillation equipment is shown prior to transport to the Idaho site. In these 2010 photographs, unexploded ordnance were collected and then detonated onsite at the Mass Detonation Area.

260

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

Science Conference Proceedings (OSTI)

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

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

2010-10-28T23:59:59.000Z

Note: This page contains sample records for the topic "disposition radioactive materials" 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

Modeling most likely pathways for smuggling radioactive and special nuclear materials on a worldwide multimodal transportation network  

Science Conference Proceedings (OSTI)

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

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

2010-01-01T23:59:59.000Z

262

NRC comprehensive records disposition schedule  

SciTech Connect

Title 44 United States Code, Public Printing and Documents,'' regulations cited in the General Services Administration's (GSA) Federal Information Resources Management Regulations'' (FIRMR), Part 201-9, Creation, Maintenance, and Use of Records,'' and regulation issued by the National Archives and Records Administration (NARA) in 36 CFR Chapter XII, Subchapter B, Records Management,'' require each agency to prepare and issue a comprehensive records disposition schedule that contains the NARA approved records disposition schedules for records unique to the agency and contains the NARA's General Records Schedules for records common to several or all agencies. The approved records disposition schedules specify the appropriate duration of retention and the final disposition for records created or maintained by the NRC. NUREG-0910, Rev. 2, contains NRC's Comprehensive Records Disposition Schedule,'' and the original authorized approved citation numbers issued by NARA. Rev. 2 totally reorganizes the records schedules from a functional arrangement to an arrangement by the host office. A subject index and a conversion table have also been developed for the NRC schedules to allow staff to identify the new schedule numbers easily and to improve their ability to locate applicable schedules.

Not Available

1992-03-01T23:59:59.000Z

263

Uses of ANSI/HPS N13.12-1999, "Surface and Volume Radioactivity Standards for Clearance" and Comparison with Existing Standards  

Science Conference Proceedings (OSTI)

In August of 1999, the American National Standards Institute (ANSI) approved a standard for clearance of materials contaminated with residual levels of radioactivity. "Clearance," as used in the standard, means the movement of material from the control of a regulatory agency to a use or disposition that has no further regulatory controls of any kind. The standard gives derived screening levels (DSLs) in Bq/g and Bq/cm2 for 50 radionuclides. Items or materials with residual surface and volume radioactivity levels below the DSLs can be cleared, that is, managed without regard to their residual radioactivity. Since federal agencies are to use voluntary, industry standards developed by the private sector whenever possible, the standard should play an important role in DOE's regulatory process. The thrust of this report is to explain the standard, make simple observations on its usefulness to DOE, and to explore uses of the standard within DOE facilities beyond the clearance of radioactive materials.

Stansbury, Paul S.; Strom, Daniel J.

2001-04-30T23:59:59.000Z

264

Environmental review of options for managing radioactively contaminated carbon steel  

SciTech Connect

The U.S. Department of Energy (DOE) is proposing to develop a strategy for the management of radioactively contaminated carbon steel (RCCS). Currently, most of this material either is placed in special containers and disposed of by shallow land burial in facilities designed for low-level radioactive waste (LLW) or is stored indefinitely pending sufficient funding to support alternative disposition. The growing amount of RCCS with which DOE will have to deal in the foreseeable future, coupled with the continued need to protect the human and natural environment, has led the Department to evaluate other approaches for managing this material. This environmental review (ER) describes the options that could be used for RCCS management and examines the potential environmental consequences of implementing each. Because much of the analysis underlying this document is available from previous studies, wherever possible the ER relies on incorporating the conclusions of those studies as summaries or by reference.

NONE

1996-10-01T23:59:59.000Z

265

REQUEST FOR RECORDS DISPOSITION AUTHORITY  

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

LEAVE BLANK (NARA use only) LEAVE BLANK (NARA use only) JOB NUMBER To: NATIONAL ARCHIVES & RECORDS ADMINISTRATION 8601 ADELPHI ROAD, COLLEGE PARK, MD 20740-6001 Date Received 1. FROM (Agency or establishment) NOTIFICATION TO AGENCY In accordance with the provisions of 44 U.S.C 3303a, the disposition request, including amendments is approved except for items that may be marked "disposition not approved" or "withdrawn" in column 10. 2. MAJOR SUB DIVISION 3. MINOR SUBDIVISION 4. NAME OF PERSON WITH WHOM TO CONFER 5. TELEPHONE DATE ARCHIVIST OF THE UNITED STATES 6. AGENCY CERTIFICATION I hereby certify that I am authorized to act for this agency in matters pertaining to the disposition of its records and that the records proposed for disposal on the attached______page(s) are not needed now for the business of this agency or will not be

266

Used Fuel Disposition R&D Documents | Department of Energy  

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

Used Fuel Disposition Used Fuel Disposition Research & Development » Used Fuel Disposition R&D Documents Used Fuel Disposition R&D Documents December 4, 2013 Preliminary Report on Dual-Purpose Canister Disposal Alternatives (FY13) This report documents the first phase of a multi-year project to understand the technical feasibility and logistical implications of direct disposal of spent nuclear fuel in existing dual-purpose canisters (DPCs) and other types of storage casks. October 25, 2013 Deep Borehole Disposal Research: Demonstration Site Selection Guidelines, Borehole Seals Design, and RD&D Needs Deep borehole disposal is one alternative for the disposal of spent nuclear fuel and other radioactive waste forms; identifying a site or areas with favorable geological, hydrogeological, and geochemical conditions is one of

267

Fuel Cycle Potential Waste Inventory for Disposition Rev 5 | Department of  

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

Fuel Cycle Potential Waste Inventory for Disposition Rev 5 Fuel Cycle Potential Waste Inventory for Disposition Rev 5 Fuel Cycle Potential Waste Inventory for Disposition Rev 5 The United States currently utilizes a once-through fuel cycle where used nuclear fuel is stored onsite in either wet pools or in dry storage systems with ultimate disposal envisioned in a deep mined geologic repository. This report provides an estimate of potential waste inventory and waste form characteristics for the DOE used nuclear fuel and high-level radioactive waste and a variety of commercial fuel cycle alternatives in order to support subsequent system-level evaluations of disposal system performance. Fuel Cycle Potential Waste Inventory for Disposition R5a.docx More Documents & Publications Repository Reference Disposal Concepts and Thermal Load Management Analysis

268

INFORMATION: Management Alert on Environmental Management's Select Strategy for Disposition of Savannah River Site Depleted Uranium Oxides  

SciTech Connect

The Administration and the Congress, through policy statements and passage of the American Recovery and Reinvestment Act of 2009 (Recovery Act), have signaled that they hope that proactive actions by agency Inspectors General will help ensure that Federal Recovery Act activities are transparent, effective and efficient. In that context, the purpose of this management alert is to share with you concerns that have been raised to the Office of Inspector General regarding the planned disposition of the Savannah River Site's (SRS) inventory of Depleted Uranium (DU) oxides. This inventory, generated as a by-product of the nuclear weapons production process and amounting to approximately 15,600 drums of DU oxides, has been stored at SRS for decades. A Department source we deem reliable and credible recently came to the Office of Inspector General expressing concern that imminent actions are planned that may not provide for the most cost effective disposition of these materials. During April 2009, the Department chose to use funds provided under the Recovery Act to accelerate final disposition of the SRS inventory of DU oxides. After coordination with State of Utah regulators, elected officials and the U.S. Nuclear Regulatory Commission, the Department initiated a campaign to ship the material to a facility operated by EnergySolutions in Clive, Utah. Although one shipment of a portion of the material has already been sent to the EnergySolutions facility, the majority of the product remains at SRS. As had been planned, both for the shipment already made and those planned in the near term, the EnergySolutions facility was to have been the final disposal location for the material. Recently, a member of Congress and various Utah State officials raised questions regarding the radioactive and other constituents present in the DU oxides to be disposed of at the Clive, Utah, facility. These concerns revolved around the characterization of the material and its acceptability under existing licensing criteria. As a consequence, the Governor of Utah met with Department officials to voice concerns regarding further shipments of the material and to seek return of the initial shipment of DU oxides to SRS. Utah's objections and the Department's agreement to accede to the State's demands effectively prohibit the transfer of the remaining material from South Carolina to Utah. In response, the Department evaluated its options and issued a draft decision paper on March 1, 2010, which outlined an alternative for temporary storage until the final disposition issue could be resolved. Under the terms of the proposed option, the remaining shipments from SRS are to be sent on an interim basis to a facility owned by Waste Control Specialists (WCS) in Andrews, Texas. Clearly, this choice carries with it a number of significant logistical burdens, including substantial additional costs for, among several items, repackaging at SRS, transportation to Texas, storage at the interim site, and, repackaging and transportation to the yet-to-be-determined final disposition point. The Department source expressed the concern that the proposal to store the material on an interim basis in Texas was inefficient and unnecessary, asserting: (1) that the materials could remain at SRS until a final disposition path is identified, and that this could be done safely, securely and cost effectively; and, (2) that the nature of the material was not subject to existing compliance agreements with the State of South Carolina, suggesting the viability of keeping the material in storage at SRS until a permanent disposal site is definitively established. We noted that, while the Department's decision paper referred to 'numerous project and programmatic factors that make it impractical to retain the remaining inventory at Savannah River,' it did not outline the specific issues involved nor did it provide any substantive economic or environmental analysis supporting the need for the planned interim storage action. The only apparent driver in this case was a Recovery Act-related goal esta

None

2010-04-01T23:59:59.000Z

269

IX disposition project, project management plan  

SciTech Connect

This subproject management plan defines the roles, responsibilities, and actions required for the execution of the IX Disposition Project.

WILLIAMS, N.H.

1999-05-11T23:59:59.000Z

270

Disposition Schedule: Human Radiation Experiments | Department...  

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

Schedule: Human Radiation Experiments Disposition Schedule: Human Radiation Experiments This database contains information on records collections related to human radiation...

271

WNA Working Group Position Statement on Removal from Regulatory Control of Material Containing Radioactivity - Exemption and Clearance  

SciTech Connect

The removal from regulatory control of materials containing trace levels of radioactivity, often referred to as 'exemption' or 'clearance', is of considerable importance to the nuclear industry and is subject to ongoing international debate. Its significance is indeed increasing as some sites move towards decommissioning, with much material being capable of recovery, recycling and re-use or simple disposal while maintaining the highest levels of public safety. This Statement outlines the key issues under consideration within the regulatory framework. Moreover, it identifies those aspects necessary for the successful application of a practical system of control. In this regard, the recent IAEA safety guide called Application of the Concept of Exclusion, Exemption and Clearance (RS-G-1.7) is paving the way towards implementing greater international convergence and consistency. (authors)

Saint-Pierre, S.; Coates, R. [World Nuclear Association (WNA), 22a St. James's Square London SWIY 4JH (United Kingdom)

2006-07-01T23:59:59.000Z

272

A guide for the ASME code for austenitic stainless steel containment vessels for high-level radioactive materials  

Science Conference Proceedings (OSTI)

The design and fabrication criteria recommended by the US Department of Energy (DOE) for high-level radioactive materials containment vessels used in packaging is found in Section III, Division 1, Subsection NB of the ASME Boiler and Pressure Vessel Code. This Code provides material, design, fabrication, examination, and testing specifications for nuclear power plant components. However, many of the requirements listed in the Code are not applicable to containment vessels made from austenitic stainless steel with austenitic or ferritic steel bolting. Most packaging designers, engineers, and fabricators are intimidated by the sheer volume of requirements contained in the Code; consequently, the Code is not always followed and many requirements that do apply are often overlooked during preparation of the Safety Analysis Report for Packaging (SARP) that constitutes the basis to evaluate the packaging for certification.

Raske, D.T.

1995-06-01T23:59:59.000Z

273

EA-1488: Environmental Assessment for the U-233 Disposition, Medical  

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

488: Environmental Assessment for the U-233 Disposition, 488: Environmental Assessment for the U-233 Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory, Oak Ridge, Tennessee EA-1488: Environmental Assessment for the U-233 Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory, Oak Ridge, Tennessee The purpose of the proposed action evaluated in this environmental assessment (EA) is the processing of uranium-233 (233U) stored at the Oak Ridge National Laboratory (ORNL) and other small quantities of similar material currently stored at other U. S. Department of Energy (DOE) sites in order to render it suitable for safe, long-term, economical storage. The 233U is stored within Bldg. 3019A, which is part of the Bldg. 3019

274

RECORDS DISPOSITION AUTHORIZATION STATE AGENCIES  

E-Print Network (OSTI)

RECORDS DISPOSITION AUTHORIZATION ­ STATE AGENCIES Form RC-108 (Revised 07/2011) STATE, CT 06106 www.cslib.org/publicrecords AUTHORITY: State agencies in the Executive branch and certain or Transfer Agreement), and retain pursuant to S1-390. STATE AGENCY: DIVISION / UNIT: ADDRESS (for return

Oliver, Douglas L.

275

Evaluation of solid-based separation materials for the pretreatment of radioactive wastes  

SciTech Connect

Separation science will play an important role in pretreating nuclear wastes stored at various US Department of Energy Sites. The application of separation processes offers potential economic and environmental benefits with regards to remediating these sites. For example, at the Hanford Site, the sizeable volume of radioactive wastes stored in underground tanks could be partitioned into a small volume of high-level waste (HLW) and a relatively large volume of low-level waste (LLW). After waste separation, only the smaller volume of HLW would require costly vitrification and geologic disposal. Furthermore, the quality of the remaining LLW form (e.g., grout) would be improved due to the lower inventory of radionuclides present in the LLW stream. This report investigates extraction chromatography as a possible separation process for Hanford wastes.

Lumetta, G.J.; Wagner, M.J.; Wester, D.W.; Morrey, J.R.

1993-05-01T23:59:59.000Z

276

Protocols for implementing DOE authorized release of radioactive scrap metals  

SciTech Connect

A process to implement the US Department of Energy`s (DOE) policy for authorized release of radioactive materials from DOE facilities is provided in the Draft Handbook for Controlling Release for Reuse or Recycle of Property Containing Residual Radioactive Material, published by DOE in 1997 and distributed to DOE field offices for interim use and implementation. The authorized release of such property is intended to permit its beneficial use across the entire DOE complex. A computerized management tool--P2Pro(RSM)--has been developed to aid in carrying out the release process for radioactive metals. It contains protocols for the authorized release process and relevant information to facilitate the evaluation of scrap metals for reuse and recycle. The P2Pro(RSM) protocols provide DOE and its contractors with an effective, user-friendly tool for managing authorized release activities P2Pro(RSM) is designed to be used in the Windows{sup {trademark}} environment. The protocols incorporate a relational database coupled with a graphic-user interface to guide the user through the appropriate steps so authorized release limits can be developed. With the information provided in the database, an as-low-as-reasonably-achievable (ALARA) optimization process can be easily set up and run for up to 10 alternatives for disposition of radioactive scrap metals. The results of the ALARA optimization process can be printed in a series of reports and submitted as part of the application for the authorized release of the radioactive scrap metals.

Chen, S.Y.; Arnish, J.; Kamboj, S.; Nieves, L.A. [Argonne National Lab., IL (United States). Environmental Assessment Div.

1999-11-01T23:59:59.000Z

277

Neutron Assay System for Confinement Vessel Disposition  

Science Conference Proceedings (OSTI)

Los Alamos National Laboratory has a number of spherical confinement vessels (CVs) remaining from tests involving nuclear materials. These vessels have an inner diameter of 6 feet with 1-inch thick steel walls. The goal of the Confinement Vessel Disposition (CVD) project is to remove debris and reduce contamination inside the CVs. The Confinement Vessel Assay System (CVAS) was developed to measure the amount of special nuclear material (SNM) in CVs before and after cleanout. Prior to cleanout, the system will be used to perform a verification measurement of each vessel. After cleanout, the system will be used to perform safeguards-quality assays of {le}100-g {sup 239}Pu equivalent in a vessel for safeguards termination. The CVAS has been tested and calibrated in preparation for verification and safeguards measurements.

Frame, Katherine C. [Los Alamos National Laboratory; Bourne, Mark M. [Los Alamos National Laboratory; Crooks, William J. [Los Alamos National Laboratory; Evans, Louise [Los Alamos National Laboratory; Mayo, Douglas R. [Los Alamos National Laboratory; Miko, David K. [Los Alamos National Laboratory; Salazar, William R. [Los Alamos National Laboratory; Stange, Sy [Los Alamos National Laboratory; Valdez, Jose I. [Los Alamos National Laboratory; Vigil, Georgiana M. [Los Alamos National Laboratory

2012-07-13T23:59:59.000Z

278

Derivation of guidelines for uranium residual radioactive material in soil at the former Baker Brothers, Inc., Site, Toledo, Ohio  

SciTech Connect

Residual radioactive material guidelines for uranium in soil were derived for the former Baker Brothers, Inc., site in Toledo, Ohio. This site has been identified for remedial action under the U.S. Department of Energy`s (DOE`s) Formerly Utilized Sites Remedial Action Program (FUSRAP). Single-nuclide and total-uranium guidelines were derived on the basis of the requirement that following remedial action, the 50-year committed effective dose equivalent to a hypothetical individual living or working in the immediate vicinity of the site should not exceed a dose constraint of 30 mrem/yr for the current use and likely future use scenarios or a dose limit of 100 mrem/yr for less likely future use scenarios. The DOE residual radioactive material guideline computer code, RESRAD, was used in this evaluation; RESRAD implements the methodology described in the DOE manual for establishing residual radioactive material guidelines. Three scenarios were considered; each assumed that for a period of 1,000 years following remedial action, the site would be used without radiological restrictions. The three scenarios varied with regard to the type of site use, time spent at the site by the exposed individual, and sources of food and water consumed. The evaluation indicates that the dose constraint of 30 mrem/yr would not be exceeded for uranium (including uranium-234, uranium-235, and uranium-238) within 1,000 years, provided that the soil concentration of total combined uranium (uranium-234, uranium-235, and uranium-238) at the former Baker Brothers site did not exceed 710 pCi/g for Scenario A (industrial worker, current use) or 210 pCi/g for Scenario B (resident - municipal water supply, a likely future use). The dose limit of 100 mrem/yr would not be exceeded at the site if the total uranium concentration of the soil did not exceed 500 pCi/g for Scenario C (subsistence farmer - on-site well water, a plausible but unlikely future use).

Nimmagadda, M.; Kamboj, S.; Yu, C.

1995-04-01T23:59:59.000Z

279

DOE/EIS-0240-SA-1: Supplement Analysis for the Disposition of Surplus Highly Enriched Uranium (October 2007)  

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

0-SA1 0-SA1 SUPPLEMENT ANALYSIS DISPOSITION OF SURPLUS HIGHLY ENRICHED URANIUM October 2007 U.S. Department of Energy National Nuclear Security Administration Office of Fissile Materials Disposition Washington, D.C. i TABLE OF CONTENTS 1.0 Introduction and Purpose .................................................................................................................1 2.0 Background......................................................................................................................................1 2.1 Scope of the HEU EIS............................................................................................................ 2 2.2 Status of Surplus HEU Disposition Activities .......................................................................

280

Derivation of residual radioactive material guidelines for uranium in soil at the Former Associate Aircraft Tool and Manufacturing Company Site, Fairfield, Ohio  

SciTech Connect

Residual radioactive material guidelines for uranium in soil were derived for the former Associate Aircraft Tool and Manufacturing Company site in Fairfield, Ohio. This site has been identified for remedial action under the U.S. Department of Energy`s (DOE`s) Formerly Utilized Sites Remedial Action Program (FUSRAP). Single-nuclide and total-uranium guidelines were derived on the basis of the requirement that, after remedial action, the 50-year committed effective dose equivalent to a hypothetical individual living or working in the immediate vicinity of the site should not exceed (1) 30 mrem/yr for the current-use and likely future-use scenarios or (2) 100 mrem/yr for less likely future-use scenarios. The DOE residual radioactive material (RESRAD) computer code, which implements the methodology described in the DOE manual for establishing residual radioactive material guidelines, was used in this evaluation.

Faillace, E.R.; Nimmagadda, M.; Yu, C.

1995-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "disposition radioactive materials" 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

Development of U.S. Regulations for the Transportation of Radioactive Materials - A Look Back Over the Past 40 Years  

SciTech Connect

The discussion in this Chapter is a relatively straightforward, chronological description of the development of U.S. transportation regulations for radioactive materials over the past 40 years. Although primarily based on the development of U.S. regulations for the shipment of what is now known as Type B quantities of radioactive materials, the information presented details the interactions between a number of U.S. governmental agencies, commissions, and departments, and the International Atomic Energy Agency (IAEA). For the most part, the information that follows was taken directly from the Federal Register, between 1965 and 2004, which, within the boundaries of the U.S., is considered law, or at least policy at the federal level. Starting in 1978, however, the information presented also takes a look at a series of so-called Guidance Documents, including Regulatory Guides (Reg. Guides), NUREGs, and NUREG/CRs. Developed originally by the U.S. Atomic Energy Agency (AEC), and later adapted by the U.S. Nuclear Regulatory Commission (NRC), the NUREGs and NUREG/CRs cited in this Chapter clearly specify a preferred methodology that can be used to meet the regulatory requirements of Title 10 of the Code of Federal Regulations, Part 71 (10 CFR Part 71, or, more simply, 10 CFR 71). As is appropriate for the discussion in this Chapter, the methodology preferred by the NRC, not as law but as guidance, was adapted directly from the requirements of the ASME's Boiler & Pressure Vessel Code. The information provided below is provided with little embellishment. By taking the information directly from the Federal Register, it becomes a story that tells itself. The information is self-consistent, and it provides all of the details behind the numerous policy decisions that led to the development of the U.S. regulations, as they were in their time, and as they are now.

Hafner, R S

2005-08-29T23:59:59.000Z

282

Calculation of releases of radioactive materials in gaseous and liquid effluents from pressurized water reactors (PWR-GALE Code). Revision 1  

SciTech Connect

This report revises the original issuance of NUREG-0017, ''Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors (PWR-GALE-Code)'' (April 1976), to incorporate more recent operating data now available as well as the results of a number of in-plant measurement programs at operating pressurized water reactors. The PWR-GALE Code is a computerized mathematical model for calculating the releases of radioactive material in gaseous and liquid effluents (i.e., the gaseous and liquid source terms). The US Nuclear Regulatory Commission uses the PWR-GALE Code to determine conformance with the requirements of Appendix I to 10 CFR Part 50.

Chandrasekaran, T.; Lee, J.Y.; Willis, C.A.

1985-04-01T23:59:59.000Z

283

Facility Disposition Safety Strategy RM  

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

Facility Disposition Safety Strategy Review Module Facility Disposition Safety Strategy Review Module March 2010 CD-0 O 0 OFFICE OF Facilit C CD-1 F ENVIRO Standard R ty Dispos Rev Critical Decis CD-2 M ONMENTAL Review Plan sition Saf view Module sion (CD) Ap CD March 2010 L MANAGE n (SRP) fety Strat e pplicability D-3 EMENT tegy CD-4 Post Ope eration Standard Review Plan, 2 nd Edition, March 2010 i FOREWORD The Standard Review Plan (SRP) 1 provides a consistent, predictable corporate review framework to ensure that issues and risks that could challenge the success of Office of Environmental Management (EM) projects are identified early and addressed proactively. The internal EM project review process encompasses key milestones established by DOE O 413.3A, Change 1, Program and Project Management for the Acquisition of Capital Assets, DOE-STD-1189-2008,

284

Direct conversion of surplus fissile materials, spent nuclear fuel, and other materials to high-level-waste glass  

SciTech Connect

With the end of the cold war the United States, Russia, and other countries have excess plutonium and other materials from the reductions in inventories of nuclear weapons. The United States Academy of Sciences (NAS) has recommended that these surplus fissile materials (SFMs) be processed so they are no more accessible than plutonium in spent nuclear fuel (SNF). This spent fuel standard, if adopted worldwide, would prevent rapid recovery of SFMs for the manufacture of nuclear weapons. The NAS recommended investigation of three sets of options for disposition of SFMs while meeting the spent fuel standard: (1) incorporate SFMs with highly radioactive materials and dispose of as waste, (2) partly burn the SFMs in reactors with conversion of the SFMs to SNF for disposal, and (3) dispose of the SFMs in deep boreholes. The US Government is investigating these options for SFM disposition. A new method for the disposition of SFMs is described herein: the simultaneous conversion of SFMs, SNF, and other highly radioactive materials into high-level-waste (HLW) glass. The SFMs include plutonium, neptinium, americium, and {sup 233}U. The primary SFM is plutonium. The preferred SNF is degraded SNF, which may require processing before it can be accepted by a geological repository for disposal.

Forsberg, C.W.; Elam, K.R.

1995-01-31T23:59:59.000Z

285

Disposition options for {sup 233}U  

SciTech Connect

The United States is implementing a program to dispose of excess nuclear-weapons-usable materials--including {sup 233}U. A series of studies have identified multiple {sup 233}U disposition options, and these options are described herein. Most of the options involve adding depleted uranium containing {sup 238}U to the {sup 233}U. Converting the {sup 233}U into a mixture of <12 wt % {sup 233}U in {sup 238}U converts the weapons-usable {sup 233}U into nonweapons-usable {sup 233}U. For {sup 233}U that is considered waste, further isotopic dilution to <0.66 wt % {sup 233}U in {sup 238}U minimizes potential long-term repository criticality concerns and in many cases minimizes final waste volumes.

Forsberg, C.W.; Icenhour, A.S.; Krichinsky, A.M.

1998-04-27T23:59:59.000Z

286

USING A RISK-BASED METHODOLOGY FOR THE TRANSFER OF RADIOACTIVE MATERIAL WITHIN THE SAVANNAH RIVER SITE BOUNDARY  

SciTech Connect

Shipment of radioactive materials (RAM) is discussed in the Code of Federal Regulations in parts of both 49 CFR and 10 CFR. The regulations provide the requirements and rules necessary for the safe shipment of RAM across public highways, railways, waterways, and through the air. These shipments are sometimes referred to as in-commerce shipments. Shipments of RAM entirely within the boundaries of Department of Energy sites, such as the Savannah River Site (SRS), can be made using methodology allowing provisions to maintain equivalent safety while deviating from the regulations for in-commerce shipments. These onsite shipments are known as transfers at the SRS. These transfers must follow the requirements approved in a site-specific Transportation Safety Document (TSD). The TSD defines how the site will transfer materials so that they have equivalence to the regulations. These equivalences are documented in an Onsite Safety Assessment (OSA). The OSA can show how a particular packaging used onsite is equivalent to that which would be used for an in-commerce shipment. This is known as a deterministic approach. However, when a deterministic approach is not viable, the TSD allows for a risk-based OSA to be written. These risk-based assessments show that if a packaging does not provide the necessary safety to ensure that materials are not released (during normal or accident conditions) then the worst-case release of materials does not result in a dose consequence worse than that defined for the SRS. This paper will discuss recent challenges and successes using this methodology at the SRS.

Loftin, B.; Watkins, R.; Loibl, M.

2010-06-03T23:59:59.000Z

287

The ultimate disposition of depleted uranium  

SciTech Connect

Significant amounts of the depleted uranium (DU) created by past uranium enrichment activities have been sold, disposed of commercially, or utilized by defense programs. In recent years, however, the demand for DU has become quite small compared to quantities available, and within the US Department of Energy (DOE) there is concern for any risks and/or cost liabilities that might be associated with the ever-growing inventory of this material. As a result, Martin Marietta Energy Systems, Inc. (Energy Systems), was asked to review options and to develop a comprehensive plan for inventory management and the ultimate disposition of DU accumulated at the gaseous diffusion plants (GDPs). An Energy Systems task team, under the chairmanship of T. R. Lemons, was formed in late 1989 to provide advice and guidance for this task. This report reviews options and recommends actions and objectives in the management of working inventories of partially depleted feed (PDF) materials and for the ultimate disposition of fully depleted uranium (FDU). Actions that should be considered are as follows. (1) Inspect UF{sub 6} cylinders on a semiannual basis. (2) Upgrade cylinder maintenance and storage yards. (3) Convert FDU to U{sub 3}O{sub 8} for long-term storage or disposal. This will include provisions for partial recovery of costs to offset those associated with DU inventory management and the ultimate disposal of FDU. Another recommendation is to drop the term tails'' in favor of depleted uranium'' or DU'' because the tails'' label implies that it is waste.'' 13 refs.

Not Available

1990-12-01T23:59:59.000Z

288

FUNCTIONALIZED SILICA AEROGELS: ADVANCED MATERIALS TO CAPTURE AND IMMOBILIZE RADIOACTIVE IODINE  

Science Conference Proceedings (OSTI)

To support the future expansion of nuclear energy, an effective method is needed to capture and safely store radiological iodine-129 released during reprocessing of spent nuclear fuel. Various materials have been investigated to capture and immobilize iodine. In most cases, however, the materials that are effective for capturing iodine cannot subsequently be sintered/densified to create a stable composite that could be a viable waste form. We have developed chemically modified, highly porous, silica aerogels that show sorption capacities higher than 440 mg of I2 per gram at 150 C. An iodine uptake test in dry air containing 4.2 ppm of iodine demonstrated no breakthrough after 3.5 h and indicated a decontamination factor in excess of 310. Preliminary densification tests showed that the I2-loaded aerogels retained more than 92 wt% of I2 after thermal sintering with pressure assistance at 1200 C for 30 min. These high capture and retention efficiencies for I2 can be further improved by optimizing the functionalization process and the chemistry as well as the sintering conditions.

Matyas, Josef; Fryxell, Glen E.; Busche, Brad J.; Wallace, Krys; Fifield, Leonard S.

2011-11-16T23:59:59.000Z

289

RADIOACTIVE BATTERY  

DOE Patents (OSTI)

A radioactive battery which includes a capsule containing the active material and a thermopile associated therewith is presented. The capsule is both a shield to stop the radiations and thereby make the battery safe to use, and an energy conventer. The intense radioactive decay taking place inside is converted to useful heat at the capsule surface. The heat is conducted to the hot thermojunctions of a thermopile. The cold junctions of the thermopile are thermally insulated from the heat source, so that a temperature difference occurs between the hot and cold junctions, causing an electrical current of a constant magnitude to flow.

Birden, J.H.; Jordan, K.C.

1959-11-17T23:59:59.000Z

290

Summary - Major Risk Factors Integrated Facility Disposition...  

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

& ORNL, Oak Ridge, TN EM Project: Integrated Facility Disposition Project (IFDP) ETR Report Date: August 2008 ETR-15 United States Department of Energy Office of Environmental...

291

Major Risk Factors Integrated Facility Disposition Project -...  

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

- Oak Ridge Summary - Major Risk Factors Integrated Facility Disposition Project (IFDP) Oak Ridge, TN More Documents & Publications Major Risk Factors to the Integrated...

292

Uranium Downblending and Disposition Project Technology Readiness...  

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

Centers Field Sites Power Marketing Administration Other Agencies You are here Home Uranium Downblending and Disposition Project Technology Readiness Assessment Uranium...

293

Uranium Downblending and Disposition Project Technology Readiness...  

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

Simulated Operational Environment Environment that uses a range of waste simulants for testing of a virtual prototype. iv 233 Uranium Downblending and Disposition Project...

294

Request For Records Disposition Authority: Strategic Petroleum...  

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

Authority: Strategic Petroleum Reserve Project Management Office Request For Records Disposition Authority: Strategic Petroleum Reserve Project Management Office Paper case files...

295

Weapons Dismantlement and Disposition NNSS Capabilities  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy (DOE) has tasked the WDD working group to disposition the large inventory of legacy classified weapon components scattered across the complex.

Pat Arnold

2011-12-01T23:59:59.000Z

296

Personal Property Disposition - Community Reuse Organizations...  

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

Disposition of Excess Personal Property BACKGROUND AND PURPOSE CROs have been operating asset conversion and personal property transfer programs since shortly after the passage of...

297

Evaluation of Possible Surrogates for Validation of the Oxidation Furnace for the Plutonium Disposition Project  

Science Conference Proceedings (OSTI)

The Plutonium Disposition project (PuD) is considering an alternative furnace design for direct metal oxidation (DMO) of plutonium metal to use as a feed for potential disposition routes. The proposed design will use a retort to oxidize the feed at temperatures up to 500 C. The atmosphere will be controlled using a metered mixture of oxygen, helium and argon to control the oxidation at approximately 400 torr. Since plutonium melts at 664 C, and may potentially react with retort material to form a lower melting point eutectic, the oxidation process will be controlled by metering the flow of oxygen to ensure that the bulk temperature of the material does not exceed this temperature. A batch processing time of <24 hours is desirable to meet anticipated furnace throughput requirements. The design project includes demonstration of concept in a small-scale demonstration test (i.e., small scale) and validation of design in a full-scale test. These tests are recommended to be performed using Pu surrogates due to challenges in consideration of the nature of plutonium and operational constraints required when handling large quantities of accountable material. The potential for spreading contamination and exposing workers to harmful levels of cumulative radioactive dose are motivation to utilize non-radioactive surrogates. Once the design is demonstrated and optimized, implementation would take place in a facility designed to accommodate these constraints. Until then, the use of surrogates would be a safer, less expensive option for the validation phase of the project. This report examines the potential for use of surrogates in the demonstration and validation of the DMO furnace for PuD. This report provides a compilation of the technical information and process requirements for the conversion of plutonium metal to oxide by burning in dry environments. Several potential surrogates were evaluated by various criteria in order to select a suitable candidate for large scale demonstration. First, the structure of the plutonium metal/oxide interface was compared to potential surrogates. Second the data for plutonium oxidation kinetics were reviewed and rates for oxidation were compared with surrogates. The criteria used as a basis for recommendation was selected in order to provide a reasonable oxidation rate during the validation phase. Several reference documents were reviewed and used to compile the information in this report. Since oxidation of large monolithic pieces of plutonium in 75% oxygen is the preferable oxidizing atmosphere for the intended process, this report does not focus on the oxidation of powders, but focuses instead on larger samples in flowing gas.

Duncan, A.

2007-12-31T23:59:59.000Z

298

DOE/EIS-0283; Surplus Plutonium Disposition Final Environmental Impact Statement (11/1999)  

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

3 of 5 3 of 5 Volume II Final Environmental Impact Statement November 1999 DOE/EIS-0283 Surplus Plutonium Disposition Final Environmental Impact Statement Volume II United States Department of Energy Office of Fissile Materials Disposition November 1999 Cover Sheet Responsible Agency: United States Department of Energy (DOE) Title: Surplus Plutonium Disposition Final Environmental Impact Statement (SPD EIS) (DOE/EIS-0283) Locations of Candidate Sites: California, Idaho, New Mexico, North Carolina, South Carolina, Tennessee, Texas, Virginia, and Washington Contacts: For further information on the SPD Final EIS contact: For information on the DOE National Environmental Policy Act (NEPA) process contact: Mr. G. Bert Stevenson, NEPA Compliance Officer Ms. Carol Borgstrom, Director Office of Fissile Materials Disposition

299

WEB RESOURCE: Radioactive Waste  

Science Conference Proceedings (OSTI)

May 8, 2007 ... This resource offers a a very broad explanation of how the Belgian Agency for Management of Radioactive Waste and Enriched Fissile Material...

300

Microsoft PowerPoint - REVWaste_Disposition_Update.061411.pptx  

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

Materials and Disposition Update Materials and Disposition Update Environmental Management Site-Specific www.em.doe.gov 1 Environmental Management Site-Specific Advisory Board Chairs' Meeting June 15, 2011 Shirley J. Olinger EM Associate Principal Deputy for Corporate Operations DOE's Waste Management Priorities Continue to manage waste inventories in a safe and compliant manner. Address high risk waste in a cost- effective manner. Maintain and optimize current disposal capability for future generations. www.em.doe.gov 2 Develop future disposal capacity in a complex environment. Promote the development of treatment and disposal alternatives in the commercial sector. Review current policies and directives and provide needed oversight. Completed Legacy TRU Sites Teledyne-Brown ARCO Energy Technology Engineering Center

Note: This page contains sample records for the topic "disposition radioactive materials" 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

SOME RESULTS OF STUDIES ON THE UPTAKE OF RADIOACTIVE WASTE MATERIALS BY MARINE AND ESTUARINE PHYTOPLANKTON ORGANISMS USING CONTINUOUS CULTURE TECHNIQUES. Technical Report XXI  

SciTech Connect

Progress is reported in studies on the uptake of radioactive waste products by phytoplackton organisms in a marine environment. Laboratory studies were made of the growth requirements of a number of phytoplankton algae. Data are included on the uptake of Ru/sup 103/ by a green algae and oysters and the uptake of Zn/sup 65/ by selected marine algae. The advantages of the use of continuous culturing techniques for the study of the uptake of radioactive materials by phytoplankton organisms are discussed. (C.H.)

Taylor, W.R.

1960-06-01T23:59:59.000Z

302

Radiological dose assessment for residual radioactive material in soil at the clean slate sites 1, 2, and 3, Tonopah Test Range  

SciTech Connect

A radiological dose assessment has been performed for Clean Slate Sites 1, 2, and 3 at the Tonopah Test Range, approximately 390 kilometers (240 miles) northwest of Las Vegas, Nevada. The assessment demonstrated that the calculated dose to hypothetical individuals who may reside or work on the Clean Slate sites, subsequent to remediation, does not exceed the limits established by the US Department of Energy for protection of members of the public and the environment. The sites became contaminated as a result of Project Roller Coaster experiments conducted in 1963 in support of the US Atomic Energy Commission (Shreve, 1964). Remediation of Clean Slate Sites 1, 2, and 3 is being performed to ensure that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works on a Clean Slate site should not exceed 100 millirems per year. The DOE residual radioactive material guideline (RESRAD) computer code was used to assess the dose. RESRAD implements the methodology described in the DOE manual for establishing residual radioactive material guidelines (Yu et al., 1993a). In May and June of 1963, experiments were conducted at Clean Slate Sites 1, 2, and 3 to study the effectiveness of earth-covered structures for reducing the dispersion of nuclear weapons material as a result of nonnuclear explosions. The experiments required the detonation of various simulated weapons using conventional chemical explosives (Shreve, 1964). The residual radioactive contamination in the surface soil consists of weapons grade plutonium, depleted uranium, and their radioactive decay products.

NONE

1997-06-01T23:59:59.000Z

303

REQUEST FOR RECORDS DISPOSITION AUTHORITY  

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

1nstrlrcrlons on reverts) 1nstrlrcrlons on reverts) ' 0 NATIONAL ARCMVES and RECORDS AD~~INISTRAT~ON (NIR) WASHINGTON, DC 20408 1. FROM (Agency or estabi~shment) Department of Energy Washington, DC 20585 . '2. MAJOR SUBDIVISION fn lccordance w i l h the provirions o f 4 4 DOE~NEVADA OPERATIONS OFFICE U.S.C. 3 3 0 3 r the disposition r e q u c ~ t , including rmtndments, i s approvtd n c t p l 3. MINOR SUBOlVlStON lor ilemr that mky be mrrkcd 'dir wition not approved' o r withdmwn' in c&mn lo. '4. NAME O F PERSON WITH WHOM TO CONFER 5. TELEPHONE Mary Ann Wallace -301 903 4353 6. AGENCY CERTIFICATION I hereby certify that I am authorized to a d for this to th#disposit-ion of its records and that the records roposed for disposal on the P now needed for the business of this agency or wil not be needed after the concurrence f

304

REQUEST FOR RECORDS DISPOSITION AUTHORITY  

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

m m - REQUEST FOR RECORDS DISPOSITION AUTHORITY (See Instructions on reverse) GENERAL SERVICES ADMINISTRATION N A T I O N A L ARCHIVES AND RECORDS SERVICE, WASHINGTON, DC 20408 1. F R O M ( A g e n c y o r e s t a b l i s h m e n t ) jepartment of Energy 2. MAJOR S U B D I V I S I O N Oak Ridse Operations Office 3. M I N O R S U B D I V I S I O N 4 . N A M E O F PERSON W I T H W H O M T O C O N F E R ( 5 . T E L E P H O N E E X T . L E A V E B L A N K - JOB N O . d/-d33P PO- ZJ - - - - p p D A T E R E C E I V E D p - NOTIFICATION TO AGENCY In accordance with the provisions of 44 U.S.C. 3303a the disposal request, including amendments, is approved except for items that may be marked "disposition not approved" or "withdrawn" in column 10. If no records are proposed for disposal, the signature of the Archivist is not required. - DATE ARCHIVIST

305

Evaluation of Calcine Disposition Path Forward  

SciTech Connect

This document describes an evaluation of the baseline and two alternative disposition paths for the final disposition of the calcine wastes stored at the Idaho Nuclear Technology and Engineering Center at the Idaho National Engineering and Environmental Laboratory. The pathways are evaluated against a prescribed set of criteria and a recommendation is made for the path forward.

Birrer, S.A.; Heiser, M.B.

2003-02-26T23:59:59.000Z

306

Evaluation of Calcine Disposition - Path Forward  

SciTech Connect

This document describes an evaluation of the baseline and two alternative disposition paths for the final disposition of the calcine wastes stored at the Idaho Nuclear Technology and Engineering Center at the Idaho National Engineering and Environmental Laboratory. The pathways are evaluated against a prescribed set of criteria and a recommendation is made for the path forward.

Steve Birrer

2003-02-01T23:59:59.000Z

307

Major Risk Factors to the Integrated Facility Disposition Project...  

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

Facility Disposition Project The scope of the Integrated Facility Disposition Project (IFDP) needs to comprehensively address a wide range of environmental management risks at the...

308

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

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

This disposition requests describe records of the History Division under the Office Executive Secretariat at the Department of Energy Headquarters REQUEST FOR RECORDS DISPOSITION...

309

U.S. and Russia Sign Plutonium Disposition Agreement | National...  

National Nuclear Security Administration (NNSA)

Agreement U.S. and Russia Sign Plutonium Disposition Agreement September 01, 2000 Washington, DC U.S. and Russia Sign Plutonium Disposition Agreement After two years of...

310

EM Makes Significant Progress on Dispositioning Transuranic Waste...  

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

Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site December 24, 2013 -...

311

Request For Records Disposition Authority | Department of Energy  

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

Authority Request For Records Disposition Authority Office of Naval Petroleum and Shale Oil Reserves Request For Records Disposition Authority More Documents & Publications...

312

Request For Records Disposition Authority | Department of Energy  

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

Naval Petroleum and Oil Shale Reserves Request For Records Disposition Authority More Documents & Publications Request For Records Disposition Authority Request For Records...

313

PROCEDURE FOR PREPARING RECORDS INVENTORY AND DISPOSITION SCHEDULES...  

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

PREPARING RECORDS INVENTORY AND DISPOSITION SCHEDULES (RIDS) PROCEDURE FOR PREPARING RECORDS INVENTORY AND DISPOSITION SCHEDULES (RIDS) This document lists the procedures for...

314

Request For Records Disposition Authority-Nuclear Weapons | Department...  

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

For Records Disposition Authority-Nuclear Weapons Request For Records Disposition Authority-Nuclear Weapons This document identifies the nuclear weapon records generated by the...

315

Topic Index to the DOE Administrative Records Disposition Schedules...  

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

Topic Index to the DOE Administrative Records Disposition Schedules Topic Index to the DOE Administrative Records Disposition Schedules Topic Index to the DOE Administrative...

316

INSPECTION OF THE ACCOUNTABILITY AND CONTROL OF SEALED RADIOACTIVE...  

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

OF THE ACCOUNTABILITY AND CONTROL OF SEALED RADIOACTIVE SOURCES AT SELECTED DEPARTMENT OF ENERGY SITES, IG-0544 Sealed radioactive sources consist of radioactive material either...

317

The effect of chlorine substitution on the disposition of polychlorinated biphenyls following dermal administration  

SciTech Connect

The fate of selected polychlorobiphenyls (PCBs) was investigated following single dermal administration (0.4 mg/kg) to determine the effects of chlorine content and position on the disposition of PCBs following dermal absorption. Single dermal doses of {sup 14}C-labeled mono-, di-, tetra- and hexachlorobiphenyls were administered to 1 cm{sup 2} areas on the backs of F-344 male rats. Distribution of radioactivity in selected tissues and excreta was determined by serial sacrifice at time points up to 2 weeks. Unabsorbed radioactivity was removed from the dose site at either sacrifice or 48 h post-dose. The time course of radioactivity in the tissues showed a dependence on rate and extent of absorption. The most rapidly absorbed PCBs reached peak tissue concentrations at early times and were cleared from the tissues rapidly. The higher chlorinated PCBs were slowly absorbed and tended to accumulate in the adipose and skin after removal of unabsorbed dose. Excretion of absorbed radioactivity varied with chlorine content ranging from 27% to ca. 100% at 2 weeks post-dose. Excretion profiles following dermal doses tended to differ from profiles following equivalent IV doses, as did the metabolite profiles in excreta. Skin slice incubation experiments suggested that first pass metabolism in the dermal dose site was responsible for metabolism and disposition differences between routes of administration. The data further suggest that the rate of absorption, and therefore the disposition of PCBs following dermal administration may be mediated, either in part or fully, by transdermal metabolism.

Garner, C. Edwin [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States)]. E-mail: cegarner@rti.org; Demeter, Jennifer [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States); Matthews, H.B. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States)

2006-10-01T23:59:59.000Z

318

I REQUEST FOR RECORDS DISPOSITION AUTHORITY  

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

REQUEST FOR RECORDS DISPOSITION AUTHORITY REQUEST FOR RECORDS DISPOSITION AUTHORITY LEAVE BL ...A (NARA use only1 JOB NUMBER TO: NATIONAL ARCHIVES & RECORDS ADMINISTRATION In accordance with the provisions of 44 U.S.C. 3303a, the Office of the Chief Information Officer disposition request, including amendments, is approved except for items that may be marked "disposition not approved" or "withdrawn" in column 10. Records Management Division N1-434-02-2 Date received 860 1 ADELPHI ROAD COLLEGE PARK, MD 20740-600 1 1. FROM (Agency or establishment) Department of Energy , ( / I 4 30 -A&&& NOTIFICATION TO AGENCY 6. AGENCY CERTIFICATION I hereby certify that I am authorized to act for this agency in matters pertaining to the disposition of its records and that the

319

Barriers and Issues Related to Achieving Final Disposition of Depleted Uranium  

Science Conference Proceedings (OSTI)

Approximately 750,000 metric tons (MT) of surplus depleted uranium (DU) in various chemical forms are stored at several Department of Energy (DOE) sites throughout the United States. Most of the DU is in the form of DU hexafluoride (DUF6) that resulted from uranium enrichment operations over the last several decades. DOE plans to convert the DUF6 to ''a more stable form'' that could be any one or combination of DU tetrafluoride (DUF4 or green salt), DU oxide (DUO3, DUO2, or DU3O8), or metal depending on the final disposition chosen for any given quantity. Barriers to final disposition of this material have existed historically and some continue today. Currently, the barriers are more related to finding uses for this material versus disposing as waste. Even though actions are beginning to convert the DUF6, ''final'' disposition of the converted material has yet to be decided. Unless beneficial uses can be implemented, DOE plans to dispose of this material as waste. This expresses the main barrier to DU disposition; DOE's strategy is to dispose unless uses can be found while the strategy should be only dispose as a last resort and make every effort to find uses. To date, only minimal research programs are underway to attempt to develop non-fuel uses for this material. Other issues requiring resolution before these inventories can reach final disposition (uses or disposal) include characterization, disposal of large quantities, storage (current and future), and treatment options. Until final disposition is accomplished, these inventories must be managed in a safe and environmentally sound manner; however, this is becoming more difficult as materials and facilities age. The most noteworthy final disposition technical issues include the development of reuse and treatment options.

Gillas, D. L.; Chambers, B. K.

2002-02-26T23:59:59.000Z

320

The Savannah River Site's liquid radioactive waste operations involves the man  

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

Site's liquid radioactive waste operations involves the management of space in the Site's Site's liquid radioactive waste operations involves the management of space in the Site's 49 underground waste tanks, including the removal of waste materials. Once water is removed from the waste tanks, two materials remain: salt and sludge waste. Removing salt waste, which fills approximately 90 percent of the tank space in the SRS tank farms, is a major step toward closing the Site's waste tanks that currently contain approximately 38 million gallons of waste. Due to the limited amount of tank space available in new-style tanks, some salt waste must be dispositioned in the interim to ensure sufficient tank space for continued sludge washing and to support the initial start-up and salt processing operations at the Salt Waste Processing Facility (SWPF).

Note: This page contains sample records for the topic "disposition radioactive materials" 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

FUEL CYCLE POTENTIAL WASTE FOR DISPOSITION  

SciTech Connect

The United States (U.S.) currently utilizes a once-through fuel cycle where used nuclear fuel (UNF) is stored on-site in either wet pools or in dry storage systems with ultimate disposal in a deep mined geologic repository envisioned. Within the Department of Energy's (DOE) Office of Nuclear Energy (DOE-NE), the Fuel Cycle Research and Development Program (FCR&D) develops options to the current commercial fuel cycle management strategy to enable the safe, secure, economic, and sustainable expansion of nuclear energy while minimizing proliferation risks by conducting research and development of advanced fuel cycles, including modified open and closed cycles. The safe management and disposition of used nuclear fuel and/or nuclear waste is a fundamental aspect of any nuclear fuel cycle. Yet, the routine disposal of used nuclear fuel and radioactive waste remains problematic. Advanced fuel cycles will generate different quantities and forms of waste than the current LWR fleet. This study analyzes the quantities and characteristics of potential waste forms including differing waste matrices, as a function of a variety of potential fuel cycle alternatives including: (1) Commercial UNF generated by uranium fuel light water reactors (LWR). Four once through fuel cycles analyzed in this study differ by varying the assumed expansion/contraction of nuclear power in the U.S; (2) Four alternative LWR used fuel recycling processes analyzed differ in the reprocessing method (aqueous vs. electro-chemical), complexity (Pu only or full transuranic (TRU) recovery) and waste forms generated; (3) Used Mixed Oxide (MOX) fuel derived from the recovered Pu utilizing a single reactor pass; and (4) Potential waste forms generated by the reprocessing of fuels derived from recovered TRU utilizing multiple reactor passes.

Jones, R.; Carter, J.

2010-10-13T23:59:59.000Z

322

FUEL CYCLE POTENTIAL WASTE FOR DISPOSITION  

SciTech Connect

The United States (U.S.) currently utilizes a once-through fuel cycle where used nuclear fuel (UNF) is stored on-site in either wet pools or in dry storage systems with ultimate disposal in a deep mined geologic repository envisioned. Within the Department of Energy's (DOE) Office of Nuclear Energy (DOE-NE), the Fuel Cycle Research and Development Program (FCR&D) develops options to the current commercial fuel cycle management strategy to enable the safe, secure, economic, and sustainable expansion of nuclear energy while minimizing proliferation risks by conducting research and development of advanced fuel cycles, including modified open and closed cycles. The safe management and disposition of used nuclear fuel and/or nuclear waste is a fundamental aspect of any nuclear fuel cycle. Yet, the routine disposal of used nuclear fuel and radioactive waste remains problematic. Advanced fuel cycles will generate different quantities and forms of waste than the current LWR fleet. This study analyzes the quantities and characteristics of potential waste forms including differing waste matrices, as a function of a variety of potential fuel cycle alternatives including: (1) Commercial UNF generated by uranium fuel light water reactors (LWR). Four once through fuel cycles analyzed in this study differ by varying the assumed expansion/contraction of nuclear power in the U.S. (2) Four alternative LWR used fuel recycling processes analyzed differ in the reprocessing method (aqueous vs. electro-chemical), complexity (Pu only or full transuranic (TRU) recovery) and waste forms generated. (3) Used Mixed Oxide (MOX) fuel derived from the recovered Pu utilizing a single reactor pass. (4) Potential waste forms generated by the reprocessing of fuels derived from recovered TRU utilizing multiple reactor passes.

Carter, J.

2011-01-03T23:59:59.000Z

323

Radioactive Materials License Commitments  

E-Print Network (OSTI)

Personnel Dosimeters Used at Nuclear Power Reactors," NUREG/CR-1204, U.S. Nuclear Regulatory Commission

324

Radioactive waste disposal package  

DOE Patents (OSTI)

A radioactive waste disposal package comprising a canister for containing vitrified radioactive waste material and a sealed outer shell encapsulating the canister. A solid block of filler material is supported in said shell and convertible into a liquid state for flow into the space between the canister and outer shell and subsequently hardened to form a solid, impervious layer occupying such space.

Lampe, Robert F. (Bethel Park, PA)

1986-01-01T23:59:59.000Z

325

Used Fuel Disposition Campaign International Activities Implementation Plan  

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

International Activities International Activities Implementation Plan Used Fuel Disposition Campaign International Activities Implementation Plan The management of used nuclear fuel and nuclear waste is required for any country using nuclear energy. This includes the storage, transportation, and disposal of low and intermediate level waste (LILW), used nuclear fuel (UNF), and high level waste (HLW). The Used Fuel Disposition Campaign (UFDC), within the U.S. Department of Energy (DOE), Office of Nuclear Energy (NE), Office of Fuel Cycle Technology (FCT), is responsible for conducting research and development pertaining to the management of these materials in the U.S. Cooperation and collaboration with other countries would be beneficial to both the U.S. and other countries through

326

Plutonium disposition via immobilization in ceramic or glass  

SciTech Connect

The management of surplus weapons plutonium is an important and urgent task with profound environmental, national, and international security implications. In the aftermath of the Cold War, Presidential Policy Directive 13, and various analyses by renown scientific, technical, and international policy organizations have brought about a focused effort within the Department of Energy to identify and implement paths for the long term disposition of surplus weapons- usable plutonium. The central goal of this effort is to render surplus weapons plutonium as inaccessible and unattractive for reuse in nuclear weapons as the much larger and growing stock of plutonium contained in spent fuel from civilian reactors. One disposition option being considered for surplus plutonium is immobilization, in which the plutonium would be incorporated into a glass or ceramic material that would ultimately be entombed permanently in a geologic repository for high-level waste.

Gray, L.W.; Kan, T.; Shaw, H.F.; Armantrout, A.

1997-03-05T23:59:59.000Z

327

Used Fuel Disposition Campaign Disposal  

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

Campaign Disposal Research and Development Roadmap Prepared for U.S. Department of Energy Used Fuel Disposition Campaign September 2012 FCR&D-USED-2011-000065 REV 1 DISCLAIMER This information was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness, of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. References herein to any specific commercial product, process, or service by trade name, trade mark, manufacturer, or

328

TRACKING SURPLUS PLUTONIUM FROM WEAPONS TO DISPOSITION  

Science Conference Proceedings (OSTI)

Supporting nuclear nonproliferation and global security principles, beginning in 1994 the United States has withdrawn more than 50 metric tons (MT) of government-controlled plutonium from potential use in nuclear weapons. The Department of Energy (DOE), including the National Nuclear Security Administration, established protocols for the tracking of this "excess" and "surplus" plutonium, and for reconciling the current storage and utilization of the plutonium to show that its management is consistent with the withdrawal policies. Programs are underway to ensure the safe and secure disposition of the materials that formed a major part of the weapons stockpile during the Cold War, and growing quantities have been disposed as waste, after which they are not included in traditional nuclear material control and accountability (NMC&A) data systems. A combination of resources is used to perform the reconciliations that form the basis for annual reporting to DOE, to U.S. Department of State, and to international partners including the International Atomic Energy Agency.

Allender, J.; Beams, J.; Sanders, K.; Myers, L.

2013-07-16T23:59:59.000Z

329

10/2/2006 SLAC-I-760-2A08Z-001-R002 RADIOACTIVE MATERIAL DECLARATION FORM  

E-Print Network (OSTI)

Radiation exposure rate: Contact: _____________mR/h 30 cm: _____________mR/h Radioactive contamination: [ ] N/A (Activated only) Internal: _______________dpm/100cm2 [ ] Unknown (External contamination must

Wechsler, Risa H.

330

Hydrocarbon evaluation proposed southeastern New Mexico radioactive material storage site Eddy County, New Mexico. Volume I. Discussion  

SciTech Connect

The proposed radioactive waste material storage site is located in the northern portion of the Delaware Basin. No hydrocarbon production exists within the current boundaries of the ''site area'', but oil and gas are being produced from 60 wells in a 368 square-mile area around the site. These wells produce from the Delaware, Bone Springs, Wolfcamp, Strawn, Atoka and Morrow zones at a total rate of about 22,682 MCF of gas and 429 barrels of oil per day. This area is considered to be potentially rich in hydrocarbon reserves and the lack of fuller development and exploration drilling is due primarily to low gas prices, lack of sales outlets and/or pipelines and moratoriums on drilling in the potash areas. Proved producing and proved nonproducing reserves are present in two wells in the Los Medanos Field area immediately adjacent to the southwest corner of the ''site area''. In addition, proved undeveloped, probable and possible reserves exist at six potential drilling locations in the Los Medanos Field. Further, probable and possible reserves were assigned to fifteen other potential drilling locations in the northwest and south-central portions of the ''site area''. Total future economically recoverable reserves projected for these wells are 62,253,244 MCF of gas and 409,628 barrels of oil. The future net undiscounted revenue to the oil operators was determined to be $48,410,821. The discounted future net revenue is $21,216,899, discounted at 10 percent per annum. The fair market value for these projected reserves is $12,730,139, assuming a fair market factor of 0.60.

1976-09-01T23:59:59.000Z

331

Final Environmental Assessment for Waste Disposition Activities at the Paducah Site Paducah, Kentucky  

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

0-347(doc)/093002 0-347(doc)/093002 1 FINDING OF NO SIGNIFICANT IMPACT WASTE DISPOSITION ACTIVITIES AT THE PADUCAH SITE PADUCAH, KENTUCKY AGENCY: U.S. DEPARTMENT OF ENERGY ACTION: FINDING OF NO SIGNIFICANT IMPACT SUMMARY: The U.S. Department of Energy (DOE) has completed an environmental assessment (DOE/EA-1339), which is incorporated herein by reference, for proposed disposition of polychlorinated biphenyl (PCB) wastes, low-level radioactive waste (LLW), mixed low- level radioactive waste (MLLW), and transuranic (TRU) waste from the Paducah Gaseous Diffusion Plant Site (Paducah Site) in Paducah, Kentucky. All of the wastes would be transported for disposal at various locations in the United States. Based on the results of the impact analysis reported in the EA, DOE has determined that the proposed action is

332

Waste Disposition Update by Christine Gelles  

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

Waste Disposition Update Waste Disposition Update Christine Gelles Associate Deputy Assistant Secretary for Waste Management (EM-30) EM SSAB Chairs Meeting Washington, DC 2 October 2012 www.em.doe.gov 2 o Waste Stream Highlights o DOE Transportation Update o Greater Than Class C (GTCC) Low Level Waste Environmental Impact Statement o Blue Ribbon Commission on America's Nuclear Future o Nuclear Regulatory Commission's LLW Regulatory Initiatives Discussion Topics www.em.doe.gov 3 Waste Stream Highlights www.em.doe.gov 4 o Within current budget outlook, it is especially critical that EM ensures safe, reliable and cost effective disposition paths exist. o The program's refocused organization and the detailed

333

User`s guide for the KBERT 1.0 code: For the knowledge-based estimation of hazards of radioactive material releases from DOE nuclear facilities  

Science Conference Proceedings (OSTI)

The possibility of worker exposure to radioactive materials during accidents at nuclear facilities is a principal concern of the DOE. The KBERT software has been developed at Sandia National Laboratories under DOE support to address this issue by assisting in the estimation of risks posed by accidents at chemical and nuclear facilities. KBERT is an acronym for Knowledge-Based system for Estimating hazards of Radioactive material release Transients. The current prototype version of KBERT focuses on calculation of doses and consequences to in-facility workers due to accidental releases of radioactivity. This report gives detailed instructions on how a user who is familiar with the design, layout and potential hazards of a facility can use KBERT to assess the risks to workers in that facility. KBERT is a tool that allows a user to simulate possible accidents and observe the predicted consequences. Potential applications of KBERT include the evaluation of the efficacy of evacuation practices, worker shielding, personal protection equipment and the containment of hazardous materials.

Browitt, D.S.; Washington, K.E.; Powers, D.A. [and others

1995-07-01T23:59:59.000Z

334

EIS-0283: Surplus Plutonium Disposition Environmental Impact Statement  

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

This EIS analyzes the potential environmental impacts associated with alternatives for the disposition of surplus plutonium.

335

DEVELOPMENT OF GLASS AND CRYSTALLINE CERAMIC FORMS FOR DISPOSITION OF EXCESS PLUTONIUM  

SciTech Connect

In the aftermath of the Cold War, the United States Department of Energy (DOE) has identified up to 50 metric tons of excess plutonium that needs to be dispositioned. The bulk of the material is slated to be blended with uranium and fabricated into a Mixed Oxide (MOX) fuel for subsequent burning in commercial nuclear reactors. Excess plutonium-containing impurity materials making it unsuitable for fabrication into MOX fuel will need to be dispositioned via other means. Glass and crystalline ceramics have been developed and studied as candidate forms to immobilize these impure plutonium feeds. A titanate-based ceramic was identified as an excellent actinide material host. This composition was based on Synroc compositions previously developed for nuclear waste immobilization. These titanate ceramics were found to be able to accommodate extremely high quantities of fissile material and exhibit excellent aqueous durability. A lanthanide borosilicate (LaBS) glass was developed to accommodate high concentrations of plutonium and to be very tolerant of impurities yet still maintain good aqueous durability. Recent testing of alkali borosilicate compositions showed promise of using these compositions to disposition lower concentrations of plutonium using existing high level waste vitrification processes. The developed waste forms all appear to be suitable for Pu disposition. Depending on the actual types and concentrations of the Pu residue streams slated for disposition, each waste form offers unique advantages.

Marra, James; Cozzi, A; Crawford, C.; Herman, C.; Marra, John; Peeler, D.

2009-09-10T23:59:59.000Z

336

Disposition of actinides released from high-level waste glass  

SciTech Connect

A series of static leach tests was conducted using glasses developed for vitrifying tank wastes at the Savannah River Site to monitor the disposition of actinide elements upon corrosion of the glasses. In these tests, glasses produced from SRL 131 and SRL 202 frits were corroded at 90{degrees}C in a tuff groundwater. Tests were conducted using crushed glass at different glass surface area-to-solution volume (S/V) ratios to assess the effect of the S/V on the solution chemistry, the corrosion of the glass, and the disposition of actinide elements. Observations regarding the effects of the S/V on the solution chemistry and the corrosion of the glass matrix have been reported previously. This paper highlights the solution analyses performed to assess how the S/V used in a static leach test affects the disposition of actinide elements between fractions that are suspended or dissolved in the solution, and retained by the altered glass or other materials.

Ebert, W.L.; Bates, J.K.; Buck, E.C.; Gong, M.; Wolf, S.F.

1994-05-01T23:59:59.000Z

337

Accelerating the disposition of transuranic waste from LANL - 9495  

Science Conference Proceedings (OSTI)

Los Alamos National Laboratory (LANL) was established during World War II with a single mission -- to design and build an atomic bomb. In the 65 years since, nuclear weapons physics, design and engineering have been the Laboratory's primary and sustaining mission. Experimental and process operations -- and associated cleanout and upgrade activities -- have generated a significant inventory of transuranic (TRU) waste that is stored at LANL's Technical Area 54, Material Disposal Area G (MDA G). When the Waste Isolation Pilot Plant (WIPP) opened its doors in 1999, LANL's TRU inventory totaled about 10,200 m{sup 3}, with a plutonium 239-equivalent curie (PE Ci) content of approximately 250,000 curies. By December 2008, a total of about 2,300 m3 (61,000 PE Ci) had been shipped to WIPP from LANL. This has resulted in a net reduction of about 1,000 m{sup 3} of TRU inventory over that time frame. This paper presents progress in dispositioning legacy and newly-generated transuranic waste (TRU) from ongoing missions at the LANL. The plans for, and lessons learned, in dispositioning several hundred high-activity TRU waste drums are reviewed. This waste population was one of the highest risks at LANL. Technical challenges in disposition of the high-activity drums are presented. These provide a preview of challenges to be addressed in dispositioning the remaining 6,800 m{sup 3} of TRU stored above ground and 2,400 m{sup 3} of TRU waste that is 'retrievably' stored below-grade. LANL is using subcontractors for much of this work and has formed a strong partnership with WIPP and its contractor to address this cleanup challenge.

Shepard, Mark D [Los Alamos National Laboratory; Stiger, Susan G [Los Alamos National Laboratory; Blankenhorn, James A [Los Alamos National Laboratory; Rael, George J [Los Alamos National Laboratory; Moody, David C [U.S DOE

2009-01-01T23:59:59.000Z

338

ICPP radioactive liquid and calcine waste technologies evaluation. Interim report  

SciTech Connect

The Department of Energy (DOE) has received spent nuclear fuel (SNF) at the Idaho Chemical Processing Plant (ICPP) for interim storage since 1951 and reprocessing since 1953. Until recently, the major activity of the ICPP has been the reprocessing of SNF to recover fissile uranium; however, changing world events have raised questions concerning the need to recover and recycle this material. In April 1992, DOE chose to discontinue reprocessing SNF for uranium recovery and shifted its focus toward the management and disposition of radioactive wastes accumulated through reprocessing activities. Currently, 1.8 million gallons of radioactive liquid wastes (1.5 million gallons of radioactive sodium-bearing liquid wastes and 0.3 million gallons of high-level liquid waste) and 3,800 cubic meters (m{sup 3}) of calcine waste are in inventory at the ICPP. Legal drivers and agreements exist obligating the INEL to develop, demonstrate, and implement technologies for safe and environmentally sound treatment and interim storage of radioactive liquid and calcine waste. Candidate treatment processes and waste forms are being evaluated using the Technology Evaluation and Analysis Methodology (TEAM) Model. This process allows decision makers to (1) identify optimum radioactive waste treatment and disposal form alternatives; (2) assess tradeoffs between various optimization criteria; (3) identify uncertainties in performance parameters; and (4) focus development efforts on options that best satisfy stakeholder concerns. The Systems Analysis technology evaluation presented in this document supports the DOE in selecting the most effective radioactive liquid and calcine waste management plan to implement in compliance with established regulations, court orders, and agreements.

Murphy, J.A.; Pincock, L.F.; Christiansen, I.N.

1994-06-01T23:59:59.000Z

339

IDENTIFYING IMPURITIES IN SURPLUS NON PIT PLUTONIUM FEEDS FOR MOX OR ALTERNATIVE DISPOSITION  

SciTech Connect

This report provides a technical basis for estimating the level of corrosion products in materials stored in DOE-STD-3013 containers based on extrapolating available chemical sample results. The primary focus is to estimate the levels of nickel, iron, and chromium impurities in plutonium-bearing materials identified for disposition in the United States Mixed Oxide fuel process.

Allender, J; Moore, E

2010-07-14T23:59:59.000Z

340

REQUEST FOR RECORDS DISPOSITION AUTHORITY  

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

Instructions on reverse) Instructions on reverse) LEAVE BLANK - GENERAL SERVICES ADMINISTRATION NATIONAL ARCHIVES AND RECORDS SERVICE, WASHINGTON, DC 20408 I . F R O M (Agency or ertabluhmentJ D A T E RECEIVED NOTIF~CATION TO AGENCY Department of Energy 2. MAJ0.R S U B D I V I S I O N I 4 . N A M E O F PERSON W I T H W H O M T O CONFER 15. TELEPHONE E X T . \OATS l A R C H l V l S T O F T H E U N I T E D STATES In accordance with the provisions of 44 U.S.C. 3303 the dispoal request. including amendmentr, is approved . 3. M I N O R S U B D I V I S I O N except for items that may be marked "disposition not approved" or "withdrawn" in column 10. If no records are proposed for disposal, the signature of the Archivist is not required. I hereby certify that I am authorized to act for this agency in matters pertaining to the disposal of the agency's records;

Note: This page contains sample records for the topic "disposition radioactive materials" 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

Submicro and Nano Structured Porous Materials for the Production of High-Intensity Exotic Radioactive Ion Beams  

E-Print Network (OSTI)

ISOLDE, the CERN Isotope Separator On-line DEvice is a unique source of low energy beams of radioactive isotopes - atomic nuclei that have too many or too few neutrons to be stable. The facility is like a small chemical factory, giving the possibility of changing one element to another, by selecting the atomic mass of the required isotope beam in the mass separator, rather as the alchemists once imagined. It produces a total of more than 1000 different isotopes from helium to radium, with half-lives down to milliseconds, by impinging a 1.4 GeV proton beam from the Proton Synchrotron Booster (PSB) onto special targets, yielding a wide variety of atomic fragments. Different components then extract the nuclei and separate them according to mass. The post-accelerator REX (Radioactive beam EXperiment) at ISOLDE accelerates the radioactive beams up to 3 MeV/u for many experiments. A wide international user radioactive ion beam (RIB) community investigates fundamental aspects of nuclear physics, particle...

Fernandes, Sandrina; Stora, Thierry

2010-01-01T23:59:59.000Z

342

DOE/EIS-0283-SA1: Supplement Analysis and Amended Record of Decision for Changes Needed To the Surplus Plutonium Disposition Program (4/24/03)  

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

3-SA1 3-SA1 April 2003 Changes Needed To The Surplus Plutonium Disposition Program SUPPLEMENT ANALYSIS AND AMENDED RECORD OF DECISION U.S. Department of Energy National Nuclear Security Administration Office of Fissile Materials Disposition Washington, D.C. Table of Contents i Table of Contents List of Figures ................................................................................................................................. ii List of Tables .................................................................................................................................. ii List of Acronyms ...........................................................................................................................

343

MRS (monitored retrievable storage) systems study Task G report: The role and functions of surface storage of radioactive material in the federal waste management system  

SciTech Connect

This is one of nine studies undertaken by contractors to the US Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM), to provide a technical basis for re-evaluating the role of a monitored retrievable storage (MRS) facility. The study investigates the functions that could be performed by surface storage of radioactive material within the federal radioactive waste management system, including enabling acceptance of spent fuel from utility owners, scheduling of waste-preparation processes within the system, enhancement of system operating reliability, and conditioning the thermal (decay heat) characteristics of spent fuel emplaced in a repository. The analysis focuses particularly on the effects of storage capacity and DOE acceptance schedule on power reactors. Figures of merit developed include the storage capacity (in metric tons of uranium (MTU)) required to be added beyond currently estimated maximum spent fuel storage capacities and its associated cost, and the number of years that spent fuel pools would remain open after last discharge (in pool-years) and the cost of this period of operation. 27 refs., 36 figs., 18 tabs.

Wood, T.W.; Short, S.M.; Woodruff, M.G.; Altenhofen, M.K.; MacKay, C.A.

1989-04-01T23:59:59.000Z

344

NRC comprehensive records disposition schedule. Revision 2  

SciTech Connect

Title 44 United States Code, ``Public Printing and Documents,`` regulations cited in the General Services Administration`s (GSA) ``Federal Information Resources Management Regulations`` (FIRMR), Part 201-9, ``Creation, Maintenance, and Use of Records,`` and regulation issued by the National Archives and Records Administration (NARA) in 36 CFR Chapter XII, Subchapter B, ``Records Management,`` require each agency to prepare and issue a comprehensive records disposition schedule that contains the NARA approved records disposition schedules for records unique to the agency and contains the NARA`s General Records Schedules for records common to several or all agencies. The approved records disposition schedules specify the appropriate duration of retention and the final disposition for records created or maintained by the NRC. NUREG-0910, Rev. 2, contains ``NRC`s Comprehensive Records Disposition Schedule,`` and the original authorized approved citation numbers issued by NARA. Rev. 2 totally reorganizes the records schedules from a functional arrangement to an arrangement by the host office. A subject index and a conversion table have also been developed for the NRC schedules to allow staff to identify the new schedule numbers easily and to improve their ability to locate applicable schedules.

Not Available

1992-03-01T23:59:59.000Z

345

NRC comprehensive records disposition schedule. Revision 3  

Science Conference Proceedings (OSTI)

Title 44 US Code, ``Public Printing and Documents,`` regulations issued by the General Service Administration (GSA) in 41 CFR Chapter 101, Subchapter B, ``Management and Use of Information and Records,`` and regulations issued by the National Archives and Records Administration (NARA) in 36 CFR Chapter 12, Subchapter B, ``Records Management,`` require each agency to prepare and issue a comprehensive records disposition schedule that contains the NARA approved records disposition schedules for records unique to the agency and contains the NARA`s General Records Schedules for records common to several or all agencies. The approved records disposition schedules specify the appropriate duration of retention and the final disposition for records created or maintained by the NRC. NUREG-0910, Rev. 3, contains ``NRC`s Comprehensive Records Disposition Schedule,`` and the original authorized approved citation numbers issued by NARA. Rev. 3 incorporates NARA approved changes and additions to the NRC schedules that have been implemented since the last revision dated March, 1992, reflects recent organizational changes implemented at the NRC, and includes the latest version of NARA`s General Records Schedule (dated August 1995).

NONE

1998-02-01T23:59:59.000Z

346

ORNL radioactive waste operations  

SciTech Connect

Since its beginning in 1943, ORNL has generated large amounts of solid, liquid, and gaseous radioactive waste material as a by-product of the basic research and development work carried out at the laboratory. The waste system at ORNL has been continually modified and updated to keep pace with the changing release requirements for radioactive wastes. Major upgrading projects are currently in progress. The operating record of ORNL waste operation has been excellent over many years. Recent surveillance of radioactivity in the Oak Ridge environs indicates that atmospheric concentrations of radioactivity were not significantly different from other areas in East Tennesseee. Concentrations of radioactivity in the Clinch River and in fish collected from the river were less than 4% of the permissible concentration and intake guides for individuals in the offsite environment. While some radioactivity was released to the environment from plant operations, the concentrations in all of the media sampled were well below established standards.

Sease, J.D.; King, E.M.; Coobs, J.H.; Row, T.H.

1982-01-01T23:59:59.000Z

347

Ceramics for Nuclear Waste Disposition  

Science Conference Proceedings (OSTI)

Oct 27, 2009 ... Materials Solutions for the Nuclear Renaissance: Ceramics for .... In-situ Decommissioning of Heavy Water Reactor Disassembly Basin:...

348

Used fuel disposition campaign international activities implementation plan.  

Science Conference Proceedings (OSTI)

The management of used nuclear fuel and nuclear waste is required for any country using nuclear energy. This includes the storage, transportation, and disposal of low and intermediate level waste (LILW), used nuclear fuel (UNF), and high level waste (HLW). The Used Fuel Disposition Campaign (UFDC), within the U.S. Department of Energy (DOE), Office of Nuclear Energy (NE), Office of Fuel Cycle Technology (FCT), is responsible for conducting research and development pertaining to the management of these materials in the U.S. Cooperation and collaboration with other countries would be beneficial to both the U.S. and other countries through information exchange and a broader participation of experts in the field. U.S. participation in international UNF and HLW exchanges leads to safe management of nuclear materials, increased security through global oversight, and protection of the environment worldwide. Such interactions offer the opportunity to develop consensus on policy, scientific, and technical approaches. Dialogue to address common technical issues helps develop an internationally recognized foundation of sound science, benefiting the U.S. and participating countries. The UNF and HLW management programs in nuclear countries are at different levels of maturity. All countries utilizing nuclear power must store UNF, mostly in wet storage, and HLW for those countries that reprocess UNF. Several countries either utilize or plan to utilize dry storage systems for UNF, perhaps for long periods of time (several decades). Geologic disposal programs are at various different states, ranging from essentially 'no progress' to selected sites and pending license applications to regulators. The table below summarizes the status of UNF and HLW management programs in several countriesa. Thus, the opportunity exists to collaborate at different levels ranging from providing expertise to those countries 'behind' the U.S. to obtaining access to information and expertise from those countries with more mature programs. The U.S. fuel cycle is a once through fuel cycle involving the direct disposal of UNF, as spent nuclear fuel, in a geologic repository (previously identified at Yucca Mountain, Nevada), following at most a few decades of storage (wet and dry). The geology at Yucca Mountain, unsaturated tuff, is unique among all countries investigating the disposal of UNF and HLW. The decision by the U.S. Department of Energy to no longer pursue the disposal of UNF at Yucca Mountain and possibly utilize very long term storage (approaching 100 years or more) while evaluating future fuel cycle alternatives for managing UNF, presents a different UNF and HLW management R&D portfolio that has been pursued in the U.S. In addition, the research and development activities managed by OCRWM have been transferred to DOE-NE. This requires a reconsideration of how the UFDC will engage in cooperative and collaborative activities with other countries. This report presents the UFDC implementation plan for international activities. The DOE Office of Civilian Radioactive Waste Management (OCRWM) has cooperated and collaborated with other countries in many different 'arenas' including the Nuclear Energy Agency (NEA) within the Organization for Economic Co-operation and Development (OECD), the International Atomic Energy Agency (IAEA), and through bilateral agreements with other countries. These international activities benefited OCRWM through the acquisition and exchange of information, database development, and peer reviews by experts from other countries. DOE-NE cooperates and collaborates with other countries in similar 'arenas' with similar objectives and realizing similar benefits. However the DOE-NE focus has not typically been in the area of UNF and HLW management. This report will first summarize these recent cooperative and collaborative activities. The manner that the UFDC will cooperate and collaborate in the future is expected to change as R&D is conducted regarding long-term storage and the potential disposal of UNF and HLW in different geolo

Nutt, W. M. (Nuclear Engineering Division)

2011-06-29T23:59:59.000Z

349

DOE/EIS-0283; Surplus Plutonium Disposition Final Environmental Impact Statement (11/1999)  

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

Summary Final Environmental Impact Statement November 1999 Summary DOE/EIS-0283 Surplus Plutonium Disposition Final Environmental Impact Statement Summary United States Department of Energy Office of Fissile Materials Disposition November 1999 Summary i Table of Contents S.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S-1 Purpose of and Need for the Proposed Action . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S-3 Issues Identified During the Scoping Period . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S-4 Issues Already Intended for Inclusion in the SPD EIS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S-4 Additional Issues That Need to Be Addressed in the SPD EIS . . . . . . . . . . . . . . . . . . . . . . . . S-5 Issues That Need to Be or Are Already Addressed Elsewhere . . . . . . . . . . . . . . . .

350

Supply and Disposition of Crude Oil and Petroleum Products  

U.S. Energy Information Administration (EIA)

Supply Disposition Ending Stocks; Field Production Renewable Fuels & Oxygenate Plant New Production Refinery & Blender Net Production Imports Net Receipts

351

Supply and Disposition of Crude Oil and Petroleum Products  

U.S. Energy Information Administration (EIA)

Supply Disposition Ending Stocks; Field Production Renewable Fuels & Oxygenate Plant Net Production Refinery & Blender Net Production Imports Net Receipts

352

U.S. and Russia Sign Plutonium Disposition Agreement | National...  

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

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

353

Supply and Disposition of Crude Oil and Petroleum Products  

U.S. Energy Information Administration (EIA)

Supply Disposition Ending Stocks; Field Production Renewable Fuels & Oxygenate Plant New Production Refinery & Blender Net Production Imports ...

354

DOE/EIS-0283; Surplus Plutonium Disposition Final Environmental Impact Statement (11/1999)  

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

2 of 5 2 of 5 Volume I - Part B Final Environmental Impact Statement November 1999 DOE/EIS-0283 Surplus Plutonium Disposition Final Environmental Impact Statement Volume I - Part B United States Department of Energy Office of Fissile Materials Disposition November 1999 Cover Sheet Responsible Agency: United States Department of Energy (DOE) Title: Surplus Plutonium Disposition Final Environmental Impact Statement (SPD EIS) (DOE/EIS-0283) Locations of Candidate Sites: California, Idaho, New Mexico, North Carolina, South Carolina, Tennessee, Texas, Virginia, and Washington Contacts: For further information on the SPD Final EIS contact: For information on the DOE National Environmental Policy Act (NEPA) process contact: Mr. G. Bert Stevenson, NEPA Compliance Officer Ms. Carol Borgstrom, Director

355

Excess Weapons Plutonium Disposition: Plutonium Packaging, Storage and Transportation and Waste Treatment, Storage and Disposal Activities  

SciTech Connect

A fifth annual Excess Weapons Plutonium Disposition meeting organized by Lawrence Livermore National Laboratory (LLNL) was held February 16-18, 2004, at the State Education Center (SEC), 4 Aerodromnya Drive, St. Petersburg, Russia. The meeting discussed Excess Weapons Plutonium Disposition topics for which LLNL has the US Technical Lead Organization responsibilities. The technical areas discussed included Radioactive Waste Treatment, Storage, and Disposal, Plutonium Oxide and Plutonium Metal Packaging, Storage and Transportation and Spent Fuel Packaging, Storage and Transportation. The meeting was conducted with a conference format using technical presentations of papers with simultaneous translation into English and Russian. There were 46 Russian attendees from 14 different Russian organizations and six non-Russian attendees, four from the US and two from France. Forty technical presentations were made. The meeting agenda is given in Appendix B and the attendance list is in Appendix C.

Jardine, L J; Borisov, G B

2004-07-21T23:59:59.000Z

356

Mission Need Statement: Calcine Disposition Project Major Systems Acquisition Project  

SciTech Connect

This document identifies the need to establish the Calcine Disposition Project to determine and implement the final disposition of calcine including characterization, retrieval, treatment (if necessary), packaging, loading, onsite interim storage pending shipment to a repository or interim storage facility, and disposition of related facilities.

J. T. Beck

2007-04-26T23:59:59.000Z

357

Supplement to the Surplus Plutonium Disposition Draft Environmental Impact Statement  

Science Conference Proceedings (OSTI)

On May 22, 1997, DOE published a Notice of Intent in the Federal Register (62 Federal Register 28009) announcing its decision to prepare an environmental impact statement (EIS) that would tier from the analysis and decisions reached in connection with the ''Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic EIS (Storage and Disposition PEIS)''. ''The Surplus Plutonium Disposition Draft Environmental Impact Statement'' (SPD Draft EIS) (DOWEIS-0283-D) was prepared in accordance with NEPA and issued in July 1998. It identified the potential environmental impacts of reasonable alternatives for the proposed siting, construction, and operation of three facilities for plutonium disposition. These three facilities would accomplish pit disassembly and conversion, immobilization, and MOX fuel fabrication. For the alternatives that included MOX fuel fabrication, the draft also described the potential environmental impacts of using from three to eight commercial nuclear reactors to irradiate MOX fuel. The potential impacts were based on a generic reactor analysis that used actual reactor data and a range of potential site conditions. In May 1998, DCE initiated a procurement process to obtain MOX fuel fabrication and reactor irradiation services. The request for proposals defined limited activities that may be performed prior to issuance of the SPD EIS Record of Decision (ROD) including non-site-specific work associated with the development of the initial design for the MOX fuel fabrication facility, and plans (paper studies) for outreach, long lead-time procurements, regulatory management, facility quality assurance, safeguards, security, fuel qualification, and deactivation. No construction on the proposed MOX facility would begin before an SPD EIS ROD is issued. In March 1999, DOE awarded a contract to Duke Engineering & Services; COGEMA, Inc.; and Stone & Webster (known as DCS) to provide the requested services. The procurement process included the environmental review specified in DOE's NEPA regulations in 10 CFR 1021.216. The six reactors selected are Catawba Nuclear Station Units 1 and 2 in South Carolina McGuire Nuclear Station Units 1 and 2 in North Carolina, and North Anna Power Station Units 1 and 2 in Virginia. The Supplement describes the potential environmental impacts of using MOX fuel in these six specific reactors named in the DCS proposal as well as other program changes made since the SPD Draft EIS was published.

N /A

1999-05-14T23:59:59.000Z

358

Surplus Plutonium Disposition (SPD) Environmental Data Summary  

Science Conference Proceedings (OSTI)

This document provides an overview of existing environmental and ecological information at areas identified as potential locations of the Savannah River Site's (SRS) Surplus Plutonium Disposition (SPD) facilities. This information is required to document existing environmental and baseline conditions from which SPD construction and operation impacts can be defined. It will be used in developing the required preoperational monitoring plan to be used at specific SPD facilities construction sites.

Fledderman, P.D.

2000-08-24T23:59:59.000Z

359

DOE - Office of Legacy Management -- University of Denver Research...  

Office of Legacy Management (LM)

of radioactive metal - circa 1965. CO.13-2 Site Disposition: Eliminated - No Authority - NRC licensed CO.13-1 Radioactive Materials Handled: Yes Primary Radioactive Materials...

360

LLNL MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement  

SciTech Connect

The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. The DOE Office of Fissile Materials Disposition (DOE-MD) has developed a dual-path strategy for disposition of surplus weapons-grade plutonium. One of the paths is to disposition surplus plutonium through irradiation of MOX fuel in commercial nuclear reactors. MOX fuel consists of plutonium and uranium oxides (PuO{sub 2} and UO{sub 2}), typically containing 95% or more UO{sub 2}. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. LLNL has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. This includes receipt and storage of PuO{sub 2} powder, fabrication of MOX fuel pellets, assembly of fuel rods and bundles, and shipping of the packaged fuel to a commercial reactor site. Support activities will take place within a Category 1 area. Building 332 will be used to receive and store the bulk PuO{sub 2} powder, fabricate MOX fuel pellets, and assemble fuel rods. Building 334 will be used to assemble, store, and ship fuel bundles. Only minor modifications would be required of Building 332. Uncontaminated glove boxes would need to be removed, petition walls would need to be removed, and minor modifications to the ventilation system would be required.

O`Connor, D.G.; Fisher, S.E.; Holdaway, R. [and others

1998-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "disposition radioactive materials" 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

Update of the Used Fuel Disposition Campaign Implementation Plan |  

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

Update of the Used Fuel Disposition Campaign Implementation Plan Update of the Used Fuel Disposition Campaign Implementation Plan Update of the Used Fuel Disposition Campaign Implementation Plan The Used Fuel Disposition Campaign will identify alternatives and conduct scientific research and technology development to enable storage, transportation, and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles. This Campaign Implementation Plan provides summary level detail describing how the Used Fuel Disposition Campaign supports achievement of the overarching Fuel Cycle Research and Development Program mission and objectives. Activities will be sufficiently flexible to accommodate any of the potential fuel cycle options for used fuel management. Update of the Used Fuel Disposition Campaign Implementation Plan

362

Understanding radioactive waste  

SciTech Connect

This document contains information on all aspects of radioactive wastes. Facts are presented about radioactive wastes simply, clearly and in an unbiased manner which makes the information readily accessible to the interested public. The contents are as follows: questions and concerns about wastes; atoms and chemistry; radioactivity; kinds of radiation; biological effects of radiation; radiation standards and protection; fission and fission products; the Manhattan Project; defense and development; uses of isotopes and radiation; classification of wastes; spent fuels from nuclear reactors; storage of spent fuel; reprocessing, recycling, and resources; uranium mill tailings; low-level wastes; transportation; methods of handling high-level nuclear wastes; project salt vault; multiple barrier approach; research on waste isolation; legal requiremnts; the national waste management program; societal aspects of radioactive wastes; perspectives; glossary; appendix A (scientific American articles); appendix B (reference material on wastes). (ATT)

Murray, R.L.

1981-12-01T23:59:59.000Z

363

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...

364

RECORDS DISPOSITION SCHEDULE: Year 2000 Project Records | Department...  

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

Year 2000 Project Records RECORDS DISPOSITION SCHEDULE: Year 2000 Project Records Year 2000 (Y2K) Project records have been created to document the effort of the Department...

365

DOE Chooses Idaho Treatment Group, LLC to Disposition Waste at...  

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

Chooses Idaho Treatment Group, LLC to Disposition Waste at the Advanced Mixed Waste Treatment Project: Contract will continue cleanup and waste operations at the Idaho Site DOE...

366

Request For Records Disposition Authority: Strategic Petroleum Reserve  

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

Request For Records Disposition Authority: Strategic Petroleum Request For Records Disposition Authority: Strategic Petroleum Reserve Project Management Office Request For Records Disposition Authority: Strategic Petroleum Reserve Project Management Office Paper case files pertaining to environmental permit applications, permits and related correspondence as well as NEPA correspondence within of the Strategic Petroleum Reserve Project Management Office (SPRPMO) Request For Records Disposition Authority: Strategic Petroleum Reserve Project Management Office More Documents & Publications 2012 Annual Planning Summary for Fossil Energy, National Energy Technology Laboratory, RMOTC, and Strategic Petroleum Reserve Field Office CX-002673: Categorical Exclusion Determination CX-009794: Categorical Exclusion Determination

367

A Model Ceramic System for Plutonium Disposition - Programmaster ...  

Science Conference Proceedings (OSTI)

As-Cast Microstructures in Alloys of U, Pu, and Zr with Minor Actinides (Np, Am) ... Irradiation Effects in Ceramics for Inert Matrix Fuel and Plutonium Disposition.

368

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

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

Crude Oil REQUEST FOR RECORDS DISPOSITION AUTHORITY More Documents & Publications Oil Overcharge Refund Cases 2003 Oil Overcharge Refund Cases 1996 Oil Overcharge Refund Cases 1999...

369

Used Fuel Disposition Campaign Disposal Research and Development...  

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

the Used Fuel Disposition Campaign (UFDC) to conduct the research and development (R&D) activities related to storage, transportation and disposal of used nuclear fuel (UNF)...

370

EIA Data: 2011 United States Coal Supply, Disposition, and Price...  

Open Energy Info (EERE)

Search Share this page on Facebook icon Twitter icon EIA Data: 2011 United States Coal Supply, Disposition, and Price Dataset Summary Description This dataset is the 2011...

371

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

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

Nuclear Power Plant Docket Records REQUEST FOR RECORDS DISPOSITION AUTHORITY More Documents & Publications PIA - Savannah River Remediation Accreditation Boundary (SRR AB) REQUEST...

372

Disposition Record Request: Oil Import Appeals Board | Department...  

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

Record Request: Oil Import Appeals Board Disposition Record Request: Oil Import Appeals Board OIAB Case Files. Records consist of company requests for relief from hardship imposed...

373

AEO2011: Total Energy Supply, Disposition, and Price Summary...  

Open Energy Info (EERE)

Total Energy Supply, Disposition, and Price Summary This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report...

374

DRAFT EM SSAB Chairs Meeting Waste Disposition Strategies...  

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

EM HQ Updates Waste Disposition Overview Christine Gelles Associate Deputy Assistant Secretary for Waste Management Office of Environmental Management EM SSAB Chairs Meeting 5...

375

Joel Case Calcine Disposition Project Federal Project Director  

Results in large life-cycle cost savings through final disposition. 6 6 Basic Hot Isostatic Pressing Process ... nuclear fuel in 1964.

376

AEO2011: Coal Supply, Disposition, and Prices This dataset comes...  

Open Energy Info (EERE)

Supply, Disposition, and Prices This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report (AEO2011). This dataset is...

377

Used Fuel Disposition Campaign Phase I Ring Compression Testing...  

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

Phase I Ring Compression Testing of High Burnup Cladding Used Fuel Disposition Campaign Phase I Ring Compression Testing of High Burnup Cladding The purpose of ring compression...

378

Additional public meeting on plutonium disposition on September...  

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

produce an oxide form of plutonium suitable for disposition and the use of mixed oxide (MOX) fuel fabricated from surplus plutonium in domestic commercial nuclear power reactors...

379

Office of UNF Disposition International Program - Strategic Plan |  

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

UNF Disposition International Program - Strategic Plan UNF Disposition International Program - Strategic Plan Office of UNF Disposition International Program - Strategic Plan The Department of Energy's Office of Nuclear Energy, Used Nuclear Fuel Disposition Research and Development Office (UFD), performs the critical mission of addressing the need for an integrated strategy that combines safe storage of spent nuclear fuel with expeditious progress toward siting and licensing a disposal facility or facilities. The UFD International Program plays a key role in this effort. International collaboration provides a forum for exchanging strategies, expertise, and technologies with other nations that have also been investigating solutions to the problems of nuclear waste disposal-information that otherwise would have

380

ANL-W MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement  

SciTech Connect

The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement (EIS). This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. The DOE Office of fissile Materials Disposition (DOE-MD) has developed a dual-path strategy for disposition of surplus weapons-grade plutonium. One of the paths is to disposition surplus plutonium through irradiation of MOX fuel in commercial nuclear reactors. MOX fuel consists of plutonium and uranium oxides (PuO{sub 2} and UO{sub 2}), typically containing 95% or more UO{sub 2}. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. The paper describes the following: Site map and the LA facility; process descriptions; resource needs; employment requirements; wastes, emissions, and exposures; accident analysis; transportation; qualitative decontamination and decommissioning; post-irradiation examination; LA fuel bundle fabrication; LA EIS data report assumptions; and LA EIS data report supplement.

O`Connor, D.G.; Fisher, S.E.; Holdaway, R. [and others

1997-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "disposition radioactive materials" 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

Corrective Action Decision Document/Closure Report for Corrective Action Unit 545: Dumps, Waste Disposal Sites, and Buried Radioactive Materials Nevada Test Site, Nevada, Revision 0  

SciTech Connect

This Corrective Action Decision Document (CADD)/Closure Report (CR) has been prepared for Corrective Action Unit (CAU) 545, Dumps, Waste Disposal Sites, and Buried Radioactive Materials, in Areas 2, 3, 9, and 20 of the Nevada Test Site, Nevada, in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management (1996, as amended February 2008). Corrective Action Unit 545 is comprised of the following eight Corrective Action Sites (CASs): 02-09-01, Mud Disposal Area 03-08-03, Mud Disposal Site 03-17-01, Waste Consolidation Site 3B 03-23-02, Waste Disposal Site 03-23-05, Europium Disposal Site 03-99-14, Radioactive Material Disposal Area 09-23-02, U-9y Drilling Mud Disposal Crater 20-19-01, Waste Disposal Site While all eight CASs are addressed in this CADD/CR, sufficient information was available for the following three CASs; therefore, a field investigation was not conducted at these sites: For CAS 03-08-03, though the potential for subsidence of the craters was judged to be extremely unlikely, the data quality objective (DQO) meeting participants agreed that sufficient information existed about disposal and releases at the site and that a corrective action of close in place with a use restriction is recommended. Sampling in the craters was not considered necessary. For CAS 03-23-02, there were no potential releases of hazardous or radioactive contaminants identified. Therefore, the Corrective Action Investigation Plan for CAU 545 concluded that: Sufficient information exists to conclude that this CAS does not exist as originally identified. Therefore, there is no environmental concern associated with CAS 03-23-02. This CAS is closed with no further action. For CAS 03-23-05, existing information about the two buried sources and lead pig was considered to be sufficient, and safety concerns existed about the stability of the crater component. Therefore, a corrective action of close in place with a use restriction is recommended, and sampling at the site was not considered necessary. The purpose of this CADD/CR is to provide justification and documentation to support the recommendation for closure of CAU 545 with no further corrective action. To achieve this, corrective action investigation (CAI) activities were performed from August 20 through November 02, 2007, as set forth in the CAU 545 Corrective Action Investigation Plan. The purpose of the CAI was to fulfill the following data needs as defined during the DQO process: Determine whether contaminants of concern (COCs) are present. If COCs are present, determine their nature and extent. Provide sufficient information and data to complete appropriate corrective actions. The CAU 545 dataset from the investigation results was evaluated based on the data quality indicator parameters. This evaluation demonstrated the quality and acceptability of the dataset for use in fulfilling the DQO data needs. Analytes detected during the CAI were evaluated against final action levels established in this CADD/CR. The results of the CAI identified no COCs at the five CASs investigated in CAU 545. As a best management practice, repair of the fence enclosing CAS 03-08-03 has been completed. Therefore, the DOE, National Nuclear Security Administration Nevada Site Office provides the following recommendations: Close in place COCs at CASs 03-08-03 and 03-23-05 with use restrictions. No further corrective action for CAU 545. No Corrective Action Plan. Corrective Action Unit 545 should be moved from Appendix III to Appendix IV of the Federal Facility Agreement and Consent Order. A Notice of Completion to the DOE, National Nuclear Security Administration Nevada Site Office is requested from the Nevada Division of Environmental Protection for closure of CAU 545.

Alfred Wickline

2008-04-01T23:59:59.000Z

382

Study of plutonium disposition using the GE Advanced Boiling Water Reactor (ABWR)  

SciTech Connect

The end of the cold war and the resulting dismantlement of nuclear weapons has resulted in the need for the U.S. to disposition 50 to 100 metric tons of excess of plutonium in parallel with a similar program in Russia. A number of studies, including the recently released National Academy of Sciences (NAS) study, have recommended conversion of plutonium into spent nuclear fuel with its high radiation barrier as the best means of providing long-term diversion resistance to this material. The NAS study {open_quotes}Management and Disposition of Excess Weapons Plutonium{close_quotes} identified light water reactor spent fuel as the most readily achievable and proven form for the disposition of excess weapons plutonium. The study also stressed the need for a U.S. disposition program which would enhance the prospects for a timely reciprocal program agreement with Russia. This summary provides the key findings of a GE study where plutonium is converted into Mixed Oxide (MOX) fuel and a 1350 MWe GE Advanced Boiling Water Reactor (ABWR) is utilized to convert the plutonium to spent fuel. The ABWR represents the integration of over 30 years of experience gained worldwide in the design, construction and operation of BWRs. It incorporates advanced features to enhance reliability and safety, minimize waste and reduce worker exposure. For example, the core is never uncovered nor is any operator action required for 72 hours after any design basis accident. Phase 1 of this study was documented in a GE report dated May 13, 1993. DOE`s Phase 1 evaluations cited the ABWR as a proven technical approach for the disposition of plutonium. This Phase 2 study addresses specific areas which the DOE authorized as appropriate for more in-depth evaluations. A separate report addresses the findings relative to the use of existing BWRs to achieve the same goal.

NONE

1994-04-30T23:59:59.000Z

383

ASSESSMENT OF RADIOACTIVE AND NON-RADIOACTIVE CONTAMINANTS FOUND IN LOW LEVEL RADIOACTIVE WASTE STREAMS  

Science Conference Proceedings (OSTI)

This paper describes and presents the findings from two studies undertaken for the European Commission to assess the long-term impact upon the environment and human health of non-radioactive contaminants found in various low level radioactive waste streams. The initial study investigated the application of safety assessment approaches developed for radioactive contaminants to the assessment of nonradioactive contaminants in low level radioactive waste. It demonstrated how disposal limits could be derived for a range of non-radioactive contaminants and generic disposal facilities. The follow-up study used the same approach but undertook more detailed, disposal system specific calculations, assessing the impacts of both the non-radioactive and radioactive contaminants. The calculations undertaken indicated that it is prudent to consider non-radioactive, as well as radioactive contaminants, when assessing the impacts of low level radioactive waste disposal. For some waste streams with relatively low concentrations of radionuclides, the potential post-closure disposal impacts from non-radioactive contaminants can be comparable with the potential radiological impacts. For such waste streams there is therefore an added incentive to explore options for recycling the materials involved wherever possible.

R.H. Little, P.R. Maul, J.S.S. Penfoldag

2003-02-27T23:59:59.000Z

384

Radioactive isotopes on the Moon  

SciTech Connect

A limited review of experiments and studies of radioactivity and isotope ratios in lunar materials is given. Observations made on the first few millimeters of the surface where the effects of solar flare particles are important, some measurements on individual rocks, and some studies of radioactivities produced deep in the lunar soil by galactic cosmic rays, are among the experiments discussed. (GHT)

Davis, R. Jr.

1975-01-01T23:59:59.000Z

385

Corrective Action Investigation Plan for Corrective Action Unit 545: Dumps, Waste Disposal Sites, and Buried Radioactive Materials Nevada Test Site, Nevada, Revision 0  

Science Conference Proceedings (OSTI)

Corrective Action Unit 545, Dumps, Waste Disposal Sites, and Buried Radioactive Materials, consists of seven inactive sites located in the Yucca Flat area and one inactive site in the Pahute Mesa area. The eight CAU 545 sites consist of craters used for mud disposal, surface or buried waste disposed within craters or potential crater areas, and sites where surface or buried waste was disposed. The CAU 545 sites were used to support nuclear testing conducted in the Yucca Flat area during the 1950s through the early 1990s, and in Area 20 in the mid-1970s. This Corrective Action Investigation Plan has been developed in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada, the U.S. Department of Energy, and the U.S. Department of Defense. Under the Federal Facility Agreement and Consent Order, this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection for approval. Fieldwork will be conducted following approval.

Alfred Wickline

2007-06-01T23:59:59.000Z

386

Waste Isolation Pilot Plant Materials Interface Interactions Test: Papers presented at the Commission of European Communities workshop on in situ testing of radioactive waste forms and engineered barriers  

Science Conference Proceedings (OSTI)

The three papers in this report were presented at the second international workshop to feature the Waste Isolation Pilot Plant (WIPP) Materials Interface Interactions Test (MIIT). This Workshop on In Situ Tests on Radioactive Waste Forms and Engineered Barriers was held in Corsendonk, Belgium, on October 13--16, 1992, and was sponsored by the Commission of the European Communities (CEC). The Studiecentrum voor Kernenergie/Centre D`Energie Nucleaire (SCK/CEN, Belgium), and the US Department of Energy (via Savannah River) also cosponsored this workshop. Workshop participants from Belgium, France, Germany, Sweden, and the United States gathered to discuss the status, results and overviews of the MIIT program. Nine of the twenty-five total workshop papers were presented on the status and results from the WIPP MIIT program after the five-year in situ conclusion of the program. The total number of published MIIT papers is now up to almost forty. Posttest laboratory analyses are still in progress at multiple participating laboratories. The first MIIT paper in this document, by Wicks and Molecke, provides an overview of the entire test program and focuses on the waste form samples. The second paper, by Molecke and Wicks, concentrates on technical details and repository relevant observations on the in situ conduct, sampling, and termination operations of the MIIT. The third paper, by Sorensen and Molecke, presents and summarizes the available laboratory, posttest corrosion data and results for all of the candidate waste container or overpack metal specimens included in the MIIT program.

Molecke, M.A.; Sorensen, N.R. [eds.] [Sandia National Labs., Albuquerque, NM (US); Wicks, G.G. [ed.] [Westinghouse Savannah River Technology Center, Aiken, SC (US)

1993-08-01T23:59:59.000Z

387

Hight-Level Waste & Facilities Disposition  

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

High-Level Waste (HLW) and Facilities Disposition Final High-Level Waste (HLW) and Facilities Disposition Final Environmental Impact Statement You are here: DOE-ID Home > Environmental Management > Idaho High-Level Waste (HLW) Table of Contents Documents are in the Adobe® PDF format and require the Adobe® Reader to access them. If you do not currently have the Acrobat Reader, you can download the Free Adobe Reader at http://get.adobe.com/reader/ Icon link to Free Adobe Acrobat Reader software * Large chapters broken down into sections Summary* Cover [ Adobe Acrobat File Size 1.48 MB] Section, 1.0 [ Adobe Acrobat File Size 612 KB] Section, 2.0 [ Adobe Acrobat File Size 251 KB] Sections, 3.0 - 3.2.1a [ Adobe Acrobat File Size 1.4 MB] Section, 3.2.1b [ Adobe Acrobat File Size 2.0 MB] Sections, 3.2.2 - 4.0 [ Adobe Acrobat File Size 1.4 MB]

388

EIS-0287: Idaho High-Level Waste and Facilities Disposition Final...  

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

Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, EIS-0287 (September 2002) EIS-0287: Idaho High-Level Waste and Facilities Disposition Final...

389

Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation  

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

Used Fuel Disposition Campaign Preliminary Quality Assurance Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation Plan Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation Plan The primary objective of this report is to determine whether the existing Fuel Cycle Technologies (FCT) Quality Assurance Program Document (QAPD) is sufficient for work to be performed in the Used Fuel Disposition Campaign (UFDC), and where the existing QAPD is not sufficient, supply recommendations for changes to the QAPD to accommodate the UFDC. The FCT QAPD provides a sound and useable foundation for the implementation of QA for UFDC R&D activities, including the application of QA in a graded approach. Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation Plan More Documents & Publications

390

Sample results from the integrated salt disposition program macrobatch 6 tank 21H qualifications MST solids sample  

Science Conference Proceedings (OSTI)

Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Integrated Salt Disposition Program (ISDP) Batch 6 processing. As part of this qualification work, SRNL performed an Actinide Removal Process (ARP) test. From this test, the residual monosodium titanate (MST) was analyzed for radionuclide uptake. The results of these analyses are reported and are within historical precedent.

Peters, T. B.

2013-02-26T23:59:59.000Z

391

SRNL - Cementitious Materials Workshop  

... the Department of Energy, ... engineers, project managers, ... status and future direction of the cement materials technology in radioactive waste ...

392

Initial report on the application of laser ablation - inductively coupled plasma mass spectrometry for the analysis of radioactive Hanford Tank Waste materials  

Science Conference Proceedings (OSTI)

Initial LA/MS analyses of Hanford tank waste samples were performed successfully using laboratory and hot cell LA/MS instrumentation systems. The experiments described in this report have demonstrated that the LA/MS data can be used to provide rapid analysis of solid, radioactive Hanford tank waste samples to identify major, minor, and trace constituents (elemental and isotopic) and fission products and radioactive isotopes. The ability to determine isotopic constituents using the LA/MS method yielded significant advantages over ICP/AES analysis by providing valuable information on fission products and radioactive constituents.

Smith, M.R.; Hartman, J.S.; Alexander, M.L.; Mendoza, A.; Hirt, E.H.; Stewart, T.L.; Hansen, M.A.; Park, W.R.; Peters, T.J.; Burghard, B.J.

1996-12-01T23:59:59.000Z

393

PROGRESS IN REDUCING THE NUCLEAR THREAT: UNITED STATES PLUTONIUM CONSOLIDATION AND DISPOSITION  

SciTech Connect

Following the end of the Cold War, the United States identified 61.5 metric tons (MT) of plutonium and larger quantities of enriched uranium that are permanently excess to use in nuclear weapons programs. The Department of Energy (DOE) also began shutting down, stabilizing, and removing inventories from production facilities that were no longer needed to support weapons programs and non-weapons activities. The storage of 'Category I' nuclear materials at Rocky Flats, Sandia National Laboratories, and several smaller sites has been terminated to reduce costs and safeguards risks. De-inventory continues at the Hanford site and the Lawrence Livermore National Laboratory. Consolidation of inventories works in concert with the permanent disposition of excess inventories, including several tonnes of plutonium that have already been disposed to waste repositories and the preparation for transfers to the planned Mixed Oxide (MOX) Fuel Fabrication Facility (for the bulk of the excess plutonium) and alternative disposition methods for material that cannot be used readily in the MOX fuel cycle. This report describes status of plutonium consolidation and disposition activities and their impacts on continuing operations, particularly at the Savannah River Site.

Allender, J.; Koenig, R.; Davies, S.

2009-06-01T23:59:59.000Z

394

EIS-0283DS Supplement to the Surplus Plutonium Disposition Draft Environmental Impact Statement, April 1999  

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

Sheet Sheet Responsible Agency: United States Department of Energy (DOE) Title: Supplement to the Surplus Plutonium Disposition Draft Environmental Impact Statement (Supplement) (DOE/EIS-0283-DS) Locations of Candidate Sites: Idaho, North Carolina, South Carolina, Texas, Virginia, and Washington Contacts: For further information on the Supplement contact: For further information on the DOE National Environmental Policy Act (NEPA) process contact: Mr. G. Bert Stevenson, NEPA Compliance Officer Office of Fissile Materials Disposition U.S. Department of Energy P.O. Box 23786 Washington, DC 20026-3786 Voice: (202) 586-5368 Ms. Carol Borgstrom, Director Office of NEPA Policy and Assistance Office of Environment, Safety and Health U.S. Department of Energy 1000 Independence Ave., SW

395

DOE/EIS-0283; Surplus Plutonium Disposition Final Environmental Impact Statement (11/1999)  

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

4 of 5 4 of 5 Final Environmental Impact Statement November 1999 Comment Response Document Volume III - Part A Cover Sheet Responsible Agency: United States Department of Energy (DOE) Title: Surplus Plutonium Disposition Final Environmental Impact Statement (SPD EIS) (DOE/EIS-0283) Locations of Candidate Sites: California, Idaho, New Mexico, North Carolina, South Carolina, Tennessee, Texas, Virginia, and Washington Contacts: For further information on the SPD Final EIS contact: For information on the DOE National Environmental Policy Act (NEPA) process contact: Mr. G. Bert Stevenson, NEPA Compliance Officer Ms. Carol Borgstrom, Director Office of Fissile Materials Disposition Office of NEPA Policy and Assistance U.S. Department of Energy Office of Environment, Safety and Health

396

DOE/EIS-0283; Surplus Plutonium Disposition Final Environmental Impact Statement (11/1999)  

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

5 of 5 5 of 5 Final Environmental Impact Statement November 1999 Comment Response Document Volume III - Part B Cover Sheet Responsible Agency: United States Department of Energy (DOE) Title: Surplus Plutonium Disposition Final Environmental Impact Statement (SPD EIS) (DOE/EIS-0283) Locations of Candidate Sites: California, Idaho, New Mexico, North Carolina, South Carolina, Tennessee, Texas, Virginia, and Washington Contacts: For further information on the SPD Final EIS contact: For information on the DOE National Environmental Policy Act (NEPA) process contact: Mr. G. Bert Stevenson, NEPA Compliance Officer Ms. Carol Borgstrom, Director Office of Fissile Materials Disposition Office of NEPA Policy and Assistance U.S. Department of Energy Office of Environment, Safety and Health

397

Weapons-grade plutonium dispositioning. Volume 2: Comparison of plutonium disposition options  

Science Conference Proceedings (OSTI)

The Secretary of Energy requested the National Academy of Sciences (NAS) Committee on International Security and Arms Control to evaluate disposition options for weapons-grade plutonium. The Idaho National Engineering Laboratory (INEL) offered to assist the NAS in this evaluation by investigating the technical aspects of the disposition options and their capability for achieving plutonium annihilation levels greater than 90%. This report was prepared for the NAS to document the gathered information and results from the requested option evaluations. Evaluations were performed for 12 plutonium disposition options involving five reactor and one accelerator-based systems. Each option was evaluated in four technical areas: (1) fuel status, (2) reactor or accelerator-based system status, (3) waste-processing status, and (4) waste disposal status. Based on these evaluations, each concept was rated on its operational capability and time to deployment. A third rating category of option costs could not be performed because of the unavailability of adequate information from the concept sponsors. The four options achieving the highest rating, in alphabetical order, are the Advanced Light Water Reactor with plutonium-based ternary fuel, the Advanced Liquid Metal Reactor with plutonium-based fuel, the Advanced Liquid Metal Reactor with uranium-plutonium-based fuel, and the Modular High Temperature Gas-Cooled Reactor with plutonium-based fuel. Of these four options, the Advanced Light Water Reactor and the Modular High Temperature Gas-Cooled Reactor do not propose reprocessing of their irradiated fuel. Time constraints and lack of detailed information did not allow for any further ratings among these four options. The INEL recommends these four options be investigated further to determine the optimum reactor design for plutonium disposition.

Brownson, D.A.; Hanson, D.J.; Blackman, H.S. [and others

1993-06-01T23:59:59.000Z

398

HEQUEST FOR Rt43RDS DISPOSITION AUTHORITY  

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

- - HEQUEST FOR Rt43RDS DISPOSITION AUTHORITY (See ~nstructions on reverse) / GENERAL SERVICES ADMINISTRATION NATIONAL ARCHIVES AND RECORDS SERVICE, WASHINGTON, D C 20408 1 . F R O M (Agency orestablishment) U.S. Department of Energy 2 . MAJOR SUBDIVISION Oak Ridge Operations Office 3. M I N O R SUBDIVISION I hereby certify that I am authorized to act for this agency in matters pertaining to the disposal of the agency's records; that the records proposed for disposal in this Request of 4 page(s) are not now needed for the business of this agency or will not be needed after the retention periods specified; and that written concurrence from the General Accounting Office, if required under the provisions of Title 8 of the GAO Manual for Guidance of Federal Agencies, is

399

REQUEST FOR RECORDS DISPOSITION AUTHORITY S  

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

S S e e Instructions o n reverse) NATIONAL ARCHIVES and RECORDS ADMINISTRATION (NIR) WASHINGTON. DC 20408 , - - 1. FROM (Agency or establishment) Department of Energy 2. MAJOR SUBDIVISION Assistant Secretary For Fossil Energy (FE-1) I 3. MINOR SUBDIVISION Office of Naval Petroleum and Shale Oil 4 . NAME OF PERSON WITH WHOM TO CON I 1 Jerry Hinkle (FE 47) 1(202)586-43 80 I I / 6. AGENCY CERTIFICATION I NOTIFICATION TO AGENCY i I In accordance with the provisions of 44 U.S.C. 3303a the disposition request, including amendments, is ap roved except for items that may be marke! "dis osition not approved" or "withdrawn" in c o L n 10. I hereby certify that I am authorized to act for this agency in yatters pertaining to of its records and that the records roposed for disposal on the attached

400

NATURE OF RADIOACTIVE WASTES  

SciTech Connect

The integrated processes of nuclear industry are considered to define the nature of wastes. Processes for recovery and preparation of U and Th fuels produce wastes containing concentrated radioactive materials which present problems of confinement and dispersal. Fundamentals of waste treatment are considered from the standpoint of processes in which radioactive materials become a factor such as naturally occurring feed materials, fission products, and elements produced by parasitic neutron capture. In addition, the origin of concentrated fission product wastes is examined, as well as characteristics of present wastes and the level of fission products in wastes. Also, comments are included on high-level wastes from processes other than solvent extraction, active gaseous wastes, and low- to intermediate-level liquid wastes. (J.R.D.)

Culler, F.L. Jr.

1959-01-26T23:59:59.000Z

Note: This page contains sample records for the topic "disposition radioactive materials" 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

Direct vitrification of plutonium-containing materials (PCM`s) with the glass material oxidation and dissolution system (GMODS)  

SciTech Connect

The end of the cold war has resulted in excess PCMs from nuclear weapons and associated production facilities. Consequently, the US government has undertaken studies to determine how best to manage and dispose of this excess material. The issues include (a) ensurance of domestic health, environment, and safety in handling, storage, and disposition, (b) international arms control agreements with Russia and other countries, and (c) economics. One major set of options is to convert the PCMs into glass for storage or disposal. The chemically inert characteristics of glasses make them a desirable chemical form for storage or disposal of radioactive materials. A glass may contain only plutonium, or it may contain plutonium along with other radioactive materials and nonradioactive materials. GMODS is a new process for the direct conversion of PCMs (i.e., plutonium metal, scrap, and residues) to glass. The plutonium content of these materials varies from a fraction of a percent to pure plutonium. GMODS has the capability to also convert other metals, ceramics, and amorphous solids to glass, destroy organics, and convert chloride-containing materials into a low-chloride glass and a secondary clean chloride salt strewn. This report is the initial study of GMODS for vitrification of PCMs as input to ongoing studies of plutonium management options. Several tasks were completed: initial analysis of process thermodynamics, initial flowsheet analysis, identification of equipment options, proof-of-principle experiments, and identification of uncertainties.

Forsberg, C.W. Beahm, E.C.; Parker, G.W.; Rudolph, J.C.; Haas, P.A.; Malling, G.F.; Elam, K.; Ott, L.

1995-10-30T23:59:59.000Z

402

Criteria and Processes for the Certification of Non-Radioactive Hazardous and Non-Hazardous Wastes  

SciTech Connect

This document details Lawrence Livermore National Laboratory's (LLNL) criteria and processes for determining if potentially volumetrically contaminated or potentially surface contaminated wastes are to be managed as material containing residual radioactivity or as non-radioactive. This document updates and replaces UCRL-AR-109662, Criteria and Procedures for the Certification of Nonradioactive Hazardous Waste (Reference 1), also known as 'The Moratorium', and follows the guidance found in the U.S. Department of Energy (DOE) document, Performance Objective for Certification of Non-Radioactive Hazardous Waste (Reference 2). The 1992 Moratorium document (UCRL-AR-109662) is three volumes and 703 pages. The first volume provides an overview of the certification process and lists the key radioanalytical methods and their associated Limits of Sensitivities. Volumes Two and Three contain supporting documents and include over 30 operating procedures, QA plans, training documents and organizational charts that describe the hazardous and radioactive waste management system in place in 1992. This current document is intended to update the previous Moratorium documents and to serve as the top-tier LLNL institutional Moratorium document. The 1992 Moratorium document was restricted to certification of Resource Conservation and Recovery Act (RCRA), State and Toxic Substances Control Act (TSCA) hazardous waste from Radioactive Material Management Areas (RMMA). This still remains the primary focus of the Moratorium; however, this document increases the scope to allow use of this methodology to certify other LLNL wastes and materials destined for off-site disposal, transfer, and re-use including non-hazardous wastes and wastes generated outside of RMMAs with the potential for DOE added radioactivity. The LLNL organization that authorizes off-site transfer/disposal of a material or waste stream is responsible for implementing the requirements of this document. The LLNL Radioactive and Hazardous Waste Management (RHWM) organization is responsible for the review and maintenance of this document. It should be noted that the DOE metal recycling moratorium is still in effect and is implemented as outlined in reference 17 when metals are being dispositioned for disposal/re-use/recycling off-site. This document follows the same methodology as described in the previously approved 1992 Moratorium document. Generator knowledge and certification are the primary means of characterization. Sampling and analysis are used when there is insufficient knowledge of a waste to determine if it contains added radioactivity. Table 1 (page 12) presents a list of LLNL's analytical methods for evaluating volumetrically contaminated waste and updates the reasonably achievable analytical-method-specific Minimum Detectable Concentrations (MDCs) for various matrices. Results from sampling and analysis are compared against the maximum MDCs for the given analytical method and the sample specific MDC to determine if the sample contains DOE added volumetric radioactivity. The evaluation of an item that has a physical form, and history of use, such that accessible surfaces may be potentially contaminated, is based on DOE Order 5400.5 (Reference 3), and its associated implementation guidance document DOE G 441.1-XX, Control and Release of Property with Residual Radioactive Material (Reference 4). The guidance document was made available for use via DOE Memorandum (Reference 5). Waste and materials containing residual radioactivity transferred off-site must meet the receiving facilities Waste Acceptance Criteria (if applicable) and be in compliance with other applicable federal or state requirements.

Dominick, J

2008-12-18T23:59:59.000Z

403

Feed Materials Production Center Waste Management Plan  

SciTech Connect

In the process of producing uranium metal products used in Department of Energy (DOE) defense programs at other DOE facilities, various types of wastes are generated at the Feed Materials Production Center (FMPC). Process wastes, both generated and stored, are discussed in the Waste Management Plan and include low-level radioactive waste (LLW), mixed hazardous/radioactive waste, and sanitary/industrial waste. Scrap metal waste and wastes requiring special remediation are also addressed in the Plan. The Waste Management Plan identifies the comprehensive programs developed to address safe storage and disposition of all wastes from past, present, and future operations at the FMPC. Waste streams discussed in this Plan are representative of the waste generated and waste types that concern worker and public health and safety. Budgets and schedules for implementation of waste disposition are also addressed. The waste streams receiving the largest amount of funding include LLW approved for shipment by DOE/ORO to the Nevada Test Site (NTS) (MgF/sub 2/, slag leach filter cake, and neutralized raffinate); remedial action wastes (waste pits, K-65 silo waste); thorium; scrap metal (contaminated and noncontaminated ferrous and copper scrap); construction rubble and soil generated from decontamination and decommissioning of outdated facilities; and low-level wastes that will be handled through the Low-Level Waste Processing and Shipping System (LLWPSS). Waste Management milestones are also provided. The Waste Management Plan is divided into eight major sections: Introduction; Site Waste and Waste Generating Process; Strategy; Projects and Operations; Waste Stream Budgets; Milestones; Quality Assurance for Waste Management; and Environmental Monitoring Program.

Watts, R.E.; Allen, T.; Castle, S.A.; Hopper, J.P.; Oelrich, R.L.

1986-12-31T23:59:59.000Z

404

Study of plutonium disposition using existing GE advanced Boiling Water Reactors  

SciTech Connect

The end of the cold war and the resulting dismantlement of nuclear weapons has resulted in the need for the US to dispose of 50 to 100 metric tons of excess of plutonium in a safe and proliferation resistant manner. A number of studies, including the recently released National Academy of Sciences (NAS) study, have recommended conversion of plutonium into spent nuclear fuel with its high radiation barrier as the best means of providing permanent conversion and long-term diversion resistance to this material. The NAS study ``Management and Disposition of Excess Weapons Plutonium identified Light Water Reactor spent fuel as the most readily achievable and proven form for the disposition of excess weapons plutonium. The study also stressed the need for a US disposition program which would enhance the prospects for a timely reciprocal program agreement with Russia. This summary provides the key findings of a GE study where plutonium is converted into Mixed Oxide (MOX) fuel and a typical 1155 MWe GE Boiling Water Reactor (BWR) is utilized to convert the plutonium to spent fuel. A companion study of the Advanced BWR has recently been submitted. The MOX core design work that was conducted for the ABWR enabled GE to apply comparable fuel design concepts and consequently achieve full MOX core loading which optimize plutonium throughput for existing BWRs.

Not Available

1994-06-01T23:59:59.000Z

405

DOE Seeks Industry Input on Nickel Disposition Strategy | Department of  

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

Industry Input on Nickel Disposition Strategy Industry Input on Nickel Disposition Strategy DOE Seeks Industry Input on Nickel Disposition Strategy March 23, 2012 - 12:00pm Addthis WASHINGTON, D.C. - The Energy Department's prime contractor, Fluor-B&W Portsmouth (FBP), managing the Portsmouth Gaseous Diffusion Plant (GDP), issued a request for Expressions of Interest (EOI) seeking industry input to support the development of an acquisition strategy for potential disposition of DOE nickel. The EOI requests technical, financial, and product market information to review the feasibility of technologies capable of decontaminating the nickel to a level indistinguishable from what is commercially available, such that it could be safely recycled and reused. The EOI scope is for 6,400 tons of nickel to be recovered from the uranium enrichment process

406

Integrated Tool Development for Used Fuel Disposition Natural System  

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

Integrated Tool Development for Used Fuel Disposition Natural Integrated Tool Development for Used Fuel Disposition Natural System Evaluation Phase I Report Integrated Tool Development for Used Fuel Disposition Natural System Evaluation Phase I Report The natural barrier system (NBS) is an integral part of a geologic nuclear waste repository. The report describes progress in development of an integrated modeling framework that can be used for systematically analyzing the performance of a natural barrier system and identifying key factors that control the performance. This framework is designed as an integrated tool for prioritization and programmatic decisions. Integrated Tool Development for Used Fuel Disposition Natural System Evaluation Phase I Report More Documents & Publications Natural System Evaluation and Tool Development FY11 Progress Report

407

AEO2011: Coal Supply, Disposition, and Prices | OpenEI  

Open Energy Info (EERE)

Supply, Disposition, and Prices Supply, Disposition, and Prices Dataset Summary Description This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report (AEO2011). This dataset is Table 15, and contains only the reference case. The dataset uses gigawatts. The data is broken down into production, net imports, consumption by sector and price. Source EIA Date Released April 26th, 2011 (3 years ago) Date Updated Unknown Keywords 2011 AEO coal coal supply disposition. prices EIA Data application/vnd.ms-excel icon AEO2011: Coal Supply, Disposition, and Prices- Reference Case (xls, 91.7 KiB) Quality Metrics Level of Review Peer Reviewed Comment Temporal and Spatial Coverage Frequency Annually Time Period 2008-2035 License License Open Data Commons Public Domain Dedication and Licence (PDDL)

408

DOE Seeks Industry Input on Nickel Disposition Strategy | Department of  

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

DOE Seeks Industry Input on Nickel Disposition Strategy DOE Seeks Industry Input on Nickel Disposition Strategy DOE Seeks Industry Input on Nickel Disposition Strategy March 23, 2012 - 12:00pm Addthis WASHINGTON, D.C. - The Energy Department's prime contractor, Fluor-B&W Portsmouth (FBP), managing the Portsmouth Gaseous Diffusion Plant (GDP), issued a request for Expressions of Interest (EOI) seeking industry input to support the development of an acquisition strategy for potential disposition of DOE nickel. The EOI requests technical, financial, and product market information to review the feasibility of technologies capable of decontaminating the nickel to a level indistinguishable from what is commercially available, such that it could be safely recycled and reused. The EOI scope is for 6,400 tons of nickel to be recovered from the uranium enrichment process

409

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE |  

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

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE April 1, 2010 - 12:00pm Addthis An operator uses robotic manipulators to process RH TRU. An operator uses robotic manipulators to process RH TRU. Idaho - The Waste Disposition Project Team at the Department of Energy's Idaho Site has continued to keep its commitment to remove remote handled (RH) transuranic (TRU) waste out of Idaho, protecting the Snake River Plain Aquifer and keeping the Office of Environmental Management's commitment to environmental clean up. In 2007, the first shipment of RH TRU waste left the gates of the Idaho Site, headed to the Waste Isolation Pilot Plant (WIPP) for disposal. In the three years since, devoted individuals on the CH2M-WG, Idaho's (CWI)

410

Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation  

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

Preliminary Quality Assurance Preliminary Quality Assurance Implementation Plan Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation Plan The primary objective of this report is to determine whether the existing Fuel Cycle Technologies (FCT) Quality Assurance Program Document (QAPD) is sufficient for work to be performed in the Used Fuel Disposition Campaign (UFDC), and where the existing QAPD is not sufficient, supply recommendations for changes to the QAPD to accommodate the UFDC. The FCT QAPD provides a sound and useable foundation for the implementation of QA for UFDC R&D activities, including the application of QA in a graded approach. Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation Plan More Documents & Publications Used Fuel Disposition Campaign International Activities Implementation Plan

411

AEO2011: Liquid Fuels Supply and Disposition | OpenEI  

Open Energy Info (EERE)

Liquid Fuels Supply and Disposition Liquid Fuels Supply and Disposition Dataset Summary Description This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report (AEO2011). This dataset is table 11, and contains only the reference case. The dataset uses million barrels per day. The data is broken down into crude oil, other petroleum supply, other non petroleum supply and liquid fuel consumption. Source EIA Date Released April 26th, 2011 (3 years ago) Date Updated Unknown Keywords 2011 AEO disposition EIA liquid fuels Supply Data application/vnd.ms-excel icon AEO2011: Liquid Fuels Supply and Disposition- Reference Case (xls, 117 KiB) Quality Metrics Level of Review Peer Reviewed Comment Temporal and Spatial Coverage Frequency Annually

412

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE |  

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

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE April 1, 2010 - 12:00pm Addthis An operator uses robotic manipulators to process RH TRU. An operator uses robotic manipulators to process RH TRU. Idaho - The Waste Disposition Project Team at the Department of Energy's Idaho Site has continued to keep its commitment to remove remote handled (RH) transuranic (TRU) waste out of Idaho, protecting the Snake River Plain Aquifer and keeping the Office of Environmental Management's commitment to environmental clean up. In 2007, the first shipment of RH TRU waste left the gates of the Idaho Site, headed to the Waste Isolation Pilot Plant (WIPP) for disposal. In the three years since, devoted individuals on the CH2M-WG, Idaho's (CWI)

413

Low Level Waste Disposition - Quantity and Inventory | Department of  

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

Low Level Waste Disposition - Quantity and Inventory Low Level Waste Disposition - Quantity and Inventory Low Level Waste Disposition - Quantity and Inventory This study has been prepared by the Used Fuel Disposition (UFD) campaign of the Fuel Cycle Research and Development (FCR&D) program. The purpose of this study is to provide an estimate of the volume of low level waste resulting from a variety of commercial fuel cycle alternatives in order to support subsequent system-level evaluations of disposal system performance. This study provides an estimate of Class A/B/C low level waste (LLW), greater than Class C (GTCC) waste, mixed LLW and mixed GTCC waste generated from the following initial set of fuel cycles and recycling processes: 1. Operations at a geologic repository based upon a once through light

414

Used Fuel Disposition Campaign Disposal Research and Development Roadmap |  

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

Used Fuel Disposition Campaign Disposal Research and Development Used Fuel Disposition Campaign Disposal Research and Development Roadmap Used Fuel Disposition Campaign Disposal Research and Development Roadmap The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technology (OFCT) has established the Used Fuel Disposition Campaign (UFDC) to conduct the research and development (R&D) activities related to storage, transportation and disposal of used nuclear fuel (UNF) and high level nuclear waste (HLW). The Mission of the UFDC is To identify alternatives and conduct scientific research and technology development to enable storage, transportation and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles. The U.S. has, for the past twenty-plus years, focused efforts on disposing

415

Low Level Waste Disposition - Quantity and Inventory | Department of  

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

Low Level Waste Disposition - Quantity and Inventory Low Level Waste Disposition - Quantity and Inventory Low Level Waste Disposition - Quantity and Inventory This study has been prepared by the Used Fuel Disposition (UFD) campaign of the Fuel Cycle Research and Development (FCR&D) program. The purpose of this study is to provide an estimate of the volume of low level waste resulting from a variety of commercial fuel cycle alternatives in order to support subsequent system-level evaluations of disposal system performance. This study provides an estimate of Class A/B/C low level waste (LLW), greater than Class C (GTCC) waste, mixed LLW and mixed GTCC waste generated from the following initial set of fuel cycles and recycling processes: 1. Operations at a geologic repository based upon a once through light

416

Integrated Tool Development for Used Fuel Disposition Natural System  

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

Integrated Tool Development for Used Fuel Disposition Natural Integrated Tool Development for Used Fuel Disposition Natural System Evaluation Phase I Report Integrated Tool Development for Used Fuel Disposition Natural System Evaluation Phase I Report The natural barrier system (NBS) is an integral part of a geologic nuclear waste repository. The report describes progress in development of an integrated modeling framework that can be used for systematically analyzing the performance of a natural barrier system and identifying key factors that control the performance. This framework is designed as an integrated tool for prioritization and programmatic decisions. Integrated Tool Development for Used Fuel Disposition Natural System Evaluation Phase I Report More Documents & Publications Natural System Evaluation and Tool Development FY11 Progress Report

417

EIA Data: 2011 United States Coal Supply, Disposition, and Price...  

Open Energy Info (EERE)

EIA Data: 2011 United States Coal Supply, Disposition, and Price This...

418

AEO2011:Total Energy Supply, Disposition, and Price Summary ...  

Open Energy Info (EERE)

AEO2011:Total Energy Supply, Disposition, and Price Summary

419

DOE Chooses Contractor to Disposition Waste at the Advanced Mixed...  

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

U.S. DEPARTMENT OF ENERGY IDAHO FALLS, IDAHO, 83403 DOE Chooses Contractor to Disposition Waste at the Advanced Mixed Waste Treatment Project (AMWTP) CH2M Hill Newport News...

420

Microsoft Word - Fuel Cycle Potential Waste Inventory for Disposition...  

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

Fuel Cycle Potential Waste Inventory for Disposition Prepared for U.S. Department of Energy Used Nuclear Fuel Joe T. Carter, SRNL Alan J. Luptak, INL Jason Gastelum, PNNL Christine...

Note: This page contains sample records for the topic "disposition radioactive materials" 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

DOE Chooses Idaho Treatment Group, LLC to Disposition Waste at...  

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

doe logo Media Contact: Brad Bugger (208) 526-0833 For Immediate Release: Friday, May 27, 2011 DOE Chooses Idaho Treatment Group, LLC to Disposition Waste at the Advanced Mixed...

422

How to deal with laboratory waste Radioactive waste  

E-Print Network (OSTI)

How to deal with laboratory waste Radioactive waste: Any laboratory waste, whether chemical or biological, containing radioactive material, should be disposed as radioactive waste. Radioactive waste should be removed from the laboratory to the departmental waste area, soon after finishing the experiment

Maoz, Shahar

423

Microsoft PowerPoint - S08-05_Leishear_Salt Disposition Initiative.ppt  

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

Blending in Nuclear Waste Tanks Blending in Nuclear Waste Tanks Bob Leishear Savannah River Remediation Salt Disposition Engineering November 17, 2010 Print Close 2 Blending in Nuclear Waste Tanks Volume 37.1 Million Gallons (Mgal) Curies 183 MCi (52%) 169 MCi (48%) 352 Million Curies (MCi) 171 MCi (49%) Sludge 34.2 Mgal (92%) 2.9 Mgal (8%) 18.4 Mgal (49%) Salt Supernate 12 MCi (3%) Saltcake 15.8 Mgal (43%) Print Close 3 Blending in Nuclear Waste Tanks Sample of Vitrified Radioactive Glass Print Close 4 Blending in Nuclear Waste Tanks SDU 3 SDU 3 SDU 2 SDU 2 SDU (Vault) 4 SDU (Vault) 4 SDU (Vault) 1 SDU (Vault) 1 Cell A Cell B Saltstone Production Facility Saltstone Production Facility Print Close 5 Blending in Nuclear Waste Tanks Print Close 6 Blending in Nuclear Waste Tanks Sludge Salt Feed Solutions Print Close 7 Experimental Strategy Scale-

424

Project Rio Blanco radioactivity and the environment  

SciTech Connect

Data are presented on radiological measurements of the environment and on documenting the transfer to a subsurface disposal well of radioactive water separated from the produced gas stream. Analysis of gas and water through the drilling well control unit revealed the presence of $sup 3$H and $sup 85$Kr in the gas and $sup 3$H, $sup 137$Cs, and $sup 90$Sr in the water. The production test, disposal system, and radiological monitoring system are described. Data on effluents are presented under the headings: gas and water production, radioactivity concentrations in gas, radioactivity concentrations in separator water samples, radioactivity concentrations in injected water volumes, and disposition of radioactivity. Tritium, $sup 39$Ar, $sup 14$C, $sup 85$Kr, and $sup 222$Rn were present in gas. Tritium, $sup 134$CCs, $sup 137$Cs, $sup 90$Sr, $sup 75$Se, and $sup 106$Ru were present in separator water samples. Data on environmental monitoring and RB-AR-2 drilling and testing are presented under the headings air sampling, air moisture and precipitation sampling, soil sampling, water sampling, Fawn Creek sediments and algae/moss samples, bioassays, aerial surveillance, and potential environmental radiation doses. (HLW)

1975-10-01T23:59:59.000Z

425

Radioactivity and Radiation  

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

Radioactivity and Radiation Radioactivity and Radiation Uranium and Its Compounds line line What is Uranium? Chemical Forms of Uranium Properties of Uranium Compounds Radioactivity and Radiation Uranium Health Effects Radioactivity and Radiation Discussion of radioactivity and radiation, uranium and radioactivity, radiological health risks of uranium isotopes and decay products. Radioactivity Radioactivity is the term used to describe the natural process by which some atoms spontaneously disintegrate, emitting both particles and energy as they transform into different, more stable atoms. This process, also called radioactive decay, occurs because unstable isotopes tend to transform into a more stable state. Radioactivity is measured in terms of disintegrations, or decays, per unit time. Common units of radioactivity

426

Radiological Assessment of Target Materials for Accelerator Transmutation of Waste (ATW) Applications  

Science Conference Proceedings (OSTI)

This paper issues the first published research of the radiation absorbed dose rate (rad-h-1) to tissue from radioactive spallation products in target materials of Ta, W, Pb, Bi, and LBE which are used in Accelerator Transmutation of Waste (ATW) applications. No previous works have provided an estimate of the absorbed dose rate (rad-h-1) from activated targets for ATW applications. The results of this paper are useful for planning the radiological safety assessment to personnel, and for the design, construction, maintenance, and disposition of target materials of high-energy particle accelerators for ATW applications. In addition, this paper provides the characterization of target materials of high-energy particle accelerators for the parameters of: 1) spallation neutron yield (neutrons/proton), 2) spallation products yield (nuclides/proton), 3) energy-dependent spallation neutron fluence distribution, 4) spallation neutron flux, 5) identification of radioactive spallation products for consideration in safety of personnel to high radiation dose rates, and 6) identification of the optimum geometrical dimensions for the target applicable to the maximum radial spallation neutron leakage from the target. Pb and Bi target materials yielded the lowest absorbed dose rates (rad-h-1) for a 10-year irradiation/50-year decay scheme, and would be the preferred target materials for consideration of the radiological safety of personnel during ATW operations. A beneficial characteristic of these target materials is that they do not produce radioactive transuranic isotopes, which have very long half-lives and require special handling and disposition requirements Furthermore, the targets are not considered High-Level Waste (HLW) such as reactor spent fuel for disposal purposes. It is a basic ATW system requirement that the spallation target after it has been expended should be disposable as Class C low-level radioactive waste. Therefore, the disposal of Pb and Bi targets would be optimally beneficial to the economy and environment. Future research should relate the target performance to other system parameters, specifically solid and liquid blanket systems that contain the radioactive waste to be transmuted. The methodology of this paper may be applied to any target material of a high-energy particle accelerator. (author)

Vickers, Linda D. [BWXT, U.S. Department of Energy, Pantex Plant, P.O. Box 30020, Hwy60/FM2373, Amarillo, TX 79120-0020 (United States)

2002-07-01T23:59:59.000Z

427

SELF SINTERING OF RADIOACTIVE WASTES  

DOE Patents (OSTI)

A method is described for disposal of radioactive liquid waste materials. The wastes are mixed with clays and fluxes to form a ceramic slip and disposed in a thermally insulated container in a layer. The temperature of the layer rises due to conversion of the energy of radioactivity to heat boillng off the liquid to fomn a dry mass. The dry mass is then covered with thermal insulation, and the mass is self-sintered into a leach-resistant ceramic cake by further conversion of the energy of radioactivity to heat.

McVay, T.N.; Johnson, J.R.; Struxness, E.G.; Morgan, K.Z.

1959-12-29T23:59:59.000Z

428

Method for storing radioactive combustible waste  

DOE Patents (OSTI)

A method is described for preventing pressure buildup in sealed containers which contain radioactively contaminated combustible waste material by adding an oxide getter material to the container so as to chemically bind sorbed water and combustion product gases. (Official Gazette)

Godbee, H.W.; Lovelace, R.C.

1973-10-01T23:59:59.000Z

429

DOE - Office of Legacy Management -- Englehard Industries - MA...  

Office of Legacy Management (LM)

operations - uranium metal - under AEC license. MA.0-03-1 Site Disposition: Eliminated - NRC licensed MA.0-03-1 Radioactive Materials Handled: Yes Primary Radioactive Materials...

430

DOE - Office of Legacy Management -- South Valley Superfund Site...  

Office of Legacy Management (LM)

Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: The Department...

431

DOE - Office of Legacy Management -- Kerr McGee - 028  

Office of Legacy Management (LM)

Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: The Kerr McGee...

432

SAMPLE RESULTS FROM THE INTEGRATED SALT DISPOSITION PROGRAM MACROBATCH 5 TANK 21H QUALIFICATION SAMPLES  

Science Conference Proceedings (OSTI)

Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 5 for the Integrated Salt Disposition Project (ISDP). This document reports partial results of the analyses of samples of Tank 21H. No issues with the projected Salt Batch 5 strategy are identified. Results of the analyses of the Tank 21H samples from this report in conjunction with the findings of the previous report, indicates that the material does not display any unusual characteristics.

Peters, T.; Fink, S.

2012-03-26T23:59:59.000Z

433

Cost-effective facility disposition planning with safety and health lessons learned and good practices from the Oak Ridge Decontamination and Decommissioning Program  

SciTech Connect

An emphasis on transition and safe disposition of DOE excess facilities has brought about significant challenges to managing worker, public, and environmental risks. The transition and disposition activities involve a diverse range of hazardous facilities that are old, poorly maintained, and contain radioactive and hazardous substances, the extent of which may be unknown. In addition, many excess facilities do not have historical facility documents such as operating records, plant and instrumentation diagrams, and incident records. The purpose of this report is to present an overview of the Oak Ridge Decontamination and Decommissioning (D and D) Program, its safety performance, and associated safety and health lessons learned and good practices. Illustrative examples of these lessons learned and good practices are also provided. The primary focus of this report is on the safety and health activities and implications associated with the planning phase of Oak Ridge facility disposition projects. Section 1.0 of this report provides the background and purpose of the report. Section 2.0 presents an overview of the facility disposition activities from which the lessons learned and good practices discussed in Section 3.0 were derived.

NONE

1998-05-01T23:59:59.000Z

434

SAMPLE RESULTS FROM THE INTEGRATED SALT DISPOSITION PROGRAM MACROBATCH 5 TANK 21H QUALIFICATION MST, ESS AND PODD SAMPLES  

Science Conference Proceedings (OSTI)

Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Integrated Salt Disposition Program (ISDP) Batch 5 processing. This qualification material was a composite created from recent samples from Tank 21H and archived samples from Tank 49H to match the projected blend from these two tanks. Additionally, samples of the composite were used in the Actinide Removal Process (ARP) and extraction-scrub-strip (ESS) tests. ARP and ESS test results met expectations. A sample from Tank 21H was also analyzed for the Performance Objectives Demonstration Document (PODD) requirements. SRNL was able to meet all of the requirements, including the desired detection limits for all the PODD analytes. This report details the results of the Actinide Removal Process (ARP), Extraction-Scrub-Strip (ESS) and Performance Objectives Demonstration Document (PODD) samples of Macrobatch (Salt Batch) 5 of the Integrated Salt Disposition Program (ISDP).

Peters, T.; Fink, S.

2012-04-24T23:59:59.000Z

435

University Loaned Normal Uranium Slug Disposition Study: University survey responses. Predecisional draft  

SciTech Connect

During the 1950`s and 1960`s, the Atomic Energy Commission loaned rejected natural uranium slugs from the Savannah River Site to United States universities for use in subcritical assemblies. Currently, there are sixty-two universities holding 91,798 slugs, containing about 167 metric tons of natural uranium. It was originally planned that the universities would return the material to Fernald when they no longer required it. Fernald has not received slugs since it was shut down in 1988. The Department of Energy`s Office of Weapons and Materials Planning requested that the Planning Support Group develop information to assist them in facilitating the return of the unwanted slugs to one or more of their facilities and develop alternatives for the ultimate disposition of this material. This supplemental report to the University Loaned Normal Uranium Slug Disposition Study documents responses to and summarizes the results of a survey of fifty-eight universities. University contacts and survey responses covering loaned slug descriptions, historical information, radiological data, current status, and plans and schedules are documented.

Becker, G.W. Jr.

1992-09