DOCSLIB.ORG

IMPLEMENTATION GUIDE for Use with DOE M 435.1-1

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
IMPLEMENTATION GUIDE for Use with DOE M 435.1-1 IMPLEMENTATION GUIDE for use with DOE M 435.1-1 Chapter IV Low-Level Waste Requirements (This page intentionally left blank.) DOE G 435.1-1 IV-1 7-09-99 IV. A. Definition of Low-Level Waste. Low-level radioactive waste is radioactive waste that is not high-level radioactive waste, spent nuclear fuel, transuranic waste, byproduct material (as defined in section 11e.(2) of the Atomic Energy Act of 1954, as amended), or naturally occurring radioactive material. Objective: The objective of this requirement is to provide the criteria for determining which DOE radioactive wastes are to be managed as low-level waste in accordance with DOE M 435.1-1, Chapter IV, Low-Level Waste Requirements. Discussion: DOE M 435.1-1, Section I.1.C., Radioactive Waste Management, requires that all DOE radioactive waste shall be managed as either high-level waste, transuranic waste, or low-level waste within one of the existing Office of Environmental Management radioactive waste management programs. To assist in determining whether a particular waste stream is low-level waste, see Figure I.1, Logic Diagram for Determining Radioactive Waste Type, which accompanies the guidance for the requirement. Management of wastes containing radioactivity that do not meet or are excluded from the definition of low-level waste above, (i.e., 11e.(2) byproduct material, residual radioactive material as defined in the Uranium Mill Tailings Radiation Control Act (UMTRCA), or naturally occurring radioactive material) should continue to be managed under the provisions of the UMTRCA or DOE 5400.5, Radiation Protection of the Public and the Environment. However, DOE M 435.1-1 allows for small quantities of these wastes to be managed in accordance with this chapter. See the guidance on DOE M 435.1-1, Section IV.B.(4). Basis. The definition of low-level waste is based on, and is essentially equivalent to, the definition used in the Nuclear Waste Policy Act of 1982, as amended. The requirements analysis (see methodology discussion of Technical Basis and Considerations, Appendix A) conducted in development of DOE O 435.1 and DOE M 435.1-1 indicated the Nuclear Waste Policy Act of 1982, as amended, definition should form the basis for the Department’s definition to be consistent with the full set of legal drivers for radioactive waste management that are now in public law. This definition also is consistent with the definition in 10 CFR 61.3, NRC’s requirements for low-level waste disposal. Section 161 of the Atomic Energy Act of 1954, as amended [Section 161(b)] authorizes the Department to promulgate rules “to govern the possession and use of special nuclear material, Chapter IV - Low-Level Waste Requirements IV-2 DOE G 435.1-1 7-09-99 source material, and byproduct material” and Section 161(i) authorizes the Department to prescribe such regulations as it deems necessary to govern any activity authorized pursuant to the Atomic Energy Act of 1954, as amended, specifically including standards for the protection of health and minimization of danger to life or property. Although most sources of ionizing radiation are encompassed by the terms “byproduct material,” “source material” and “special nuclear material,” some sources, such as machine-produced radioactive material, are not. Because all ionizing radiation has the potential to cause harm, the Department does not limit its radioactive waste management requirements to situations involving byproduct, source and special nuclear material. Low-level radioactive waste is defined by what it is not. The definition provides the framework for this concept by listing the basic radioactive waste types that are not low-level waste, thereby limiting the wastes that are to be managed as low-level waste. Thus, an understanding of the definitions of high-level radioactive waste, spent nuclear fuel, transuranic waste, byproduct material, and naturally occurring radioactive material is necessary to determine whether a subject waste is to be managed as low-level waste in accordance with DOE M 435.1-1, Chapter IV. The definitions of and relevant guidance on high-level waste (see Chapter II.A) and transuranic waste (see Chapter III.A) are contained in the guidance on Chapters II and III of the Manual, respectively. The guidance on definitions in Chapters II and III should be consulted first for making a determination on how to properly manage a suspect waste stream. Specific waste determination cases discussed in that guidance may provide assistance on deciding which radioactive wastes are to be managed as low-level waste. Many of these specific waste stream decisions are referenced and/or discussed again in the following guidance on the definition of low- level waste. High-Level Waste Exclusion. High-level waste is the first type of radioactive waste excluded from the definition of low-level waste. Guidance on the definition of High-Level Waste in Chapter II clarifies the meaning of that term for applicability to certain DOE waste streams. That guidance should be consulted first for determining if a waste stream should be managed as high-level waste. Those waste streams that should be managed as low-level waste must meet the requirements of DOE M 435.1-1, Chapter IV. Radioactive waste that meets the requirements of waste incidental to reprocessing, either by citation or evaluation, is excluded from the scope of high-level waste. It is the intent of the requirements of DOE O 435.1 and DOE M 435.1-1 that wastes which are excluded from the high-level waste management requirements because they have been determined to be not high- level waste through the waste incidental to reprocessing determination process and contain transuranics less than 100 nCi/g are low-level waste to be managed in accordance with Chapter IV of DOE M 435.1-1. (See guidance on Waste Incidental to Reprocessing, DOE M 435.1-1, Section II.B). Chapter IV - Low-Level Waste Requirements DOE G 435.1-1 IV-3 7-09-99 Example: At the Hanford Site the high-level waste program used the evaluation process to gain NRC support for on-site disposal of the low-activity waste stream removed from the high-level waste tanks as waste incidental to reprocessing. The on-site disposal facility shall meet the low-level waste requirements for disposal in accordance with DOE M 435.1-1. Spent Nuclear Fuel Exclusion. Spent nuclear fuel is excluded from the definition of low-level waste. Spent nuclear fuel is defined in the Nuclear Waste Policy Act of 1982, as amended, as “...fuel that has been withdrawn from a nuclear reactor following irradiation, the constituent elements of which have not been separated by reprocessing.” The term refers to the spent fuel rods and assemblies as they are managed upon removal from a reactor, especially in terms of the applicability of provisions for management of spent fuel in the Nuclear Waste Policy Act of 1982, as amended. Guidance on the definition of high-level waste for Chapter II, DOE M 435.1-1 clarifies the meaning of spent nuclear fuel for applicability to certain Department waste streams that could fit the description of spent nuclear fuel. That guidance should be consulted first for determining whether one of these waste streams is to be managed as high-level waste. Those waste streams that are determined should be managed as low-level waste must meet the requirements of DOE M 435.1-1, Chapter IV. Example: Site Q has irradiated target elements in long-term storage that must be disposed. The targets contain neither fissile material, nor do they meet the definition of transuranic waste. The targets are managed for disposal as low-level waste. Transuranic Waste Exclusion. Transuranic waste is excluded from the definition of low-level waste. As mentioned, the definition of transuranic waste is further explained in the guidance on Requirement III.A. That guidance clarifies the applicability of the term transuranic waste for certain DOE radioactive waste streams. The guidance should be consulted first for determining if a waste stream should be managed as transuranic waste. Those streams that should be managed as low-level waste must meet the requirements of Chapter IV, DOE M 435.1-1. Three exceptions to the definition of transuranic waste are discussed in the guidance for transuranic waste requirements (DOE M 435.1-1, Section III.A). The first exception is high-level waste which, as discussed previously, is also excluded from the definition of low-level waste. The second exception is waste that DOE, with the concurrence of the EPA Administrator, has determined does not need the degree of isolation that is provided by implementation of the disposal requirements of 40 CFR Part 191. This waste is to be managed as low-level waste in accordance with Chapter IV of DOE M 435.1-1. The third exception applies to waste generated by commercial activities that have concentrations of radionuclides that would result in categorization as transuranic waste. As long as the waste is not high-level waste, it could be accepted (with NRC approval not to invoke 40 CFR Part 191) as Greater-than-Class-C (GTCC) low-level waste per the classification system in 10 CFR 61.55. This waste is to be managed as Chapter IV - Low-Level Waste Requirements IV-4 DOE G 435.1-1 7-09-99 low-level waste in accordance with Chapter IV of DOE M 435.1-1. However, GTCC waste is to be disposed of in a facility licensed by the U.S. Nuclear Regulatory Commission (See the guidance on Complex-Wide Low-Level Waste Management Program concerning management of commercial (NRC licensed) GTCC, DOE M 435.1-1, Section IV.C.).
Load more

Recommended publications
  • Sixth National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management
    October 2017 United States of America Sixth National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management U.S. Department of Energy In Cooperation with the U.S. Nuclear Regulatory Commission U.S. Environmental Protection Agency U.S. Department of State This page intentionally left blank. U.S. Sixth National Report-Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management ABSTRACT AND ACKNOWLEDGEMENT The United States of America (U.S.) ratified the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (Joint Convention) on April 9, 2003. The Joint Convention establishes an international peer review process among Contracting Parties and provides incentives for nations to take appropriate steps to bring their spent fuel and radioactive waste management activities into compliance with general safety standards and practices. The U.S. participated in Review Meetings of the Contracting Parties to the Joint Convention in November 2003, May 2006, May 2009, May 2012 and May 2015 in Vienna, Austria. This Sixth National Report, an update of the U.S. Fifth National Report prepared under the Joint Convention in September 2014, documents spent fuel and radioactive waste management safety in the U.S. under the terms of the Joint Convention. The U.S. Government prepared this report for review by the Contracting Parties. The U.S. complies with the terms of the Joint Convention. An extensive U.S. legal and regulatory structure ensures the safety of spent fuel and radioactive waste management.
    [Show full text]
  • DOE's Remote-Handled TRU Waste Characterization Program
    DOE/WIPP-02-3214 REMOTE-HANDLED TRU WASTE CHARACTERIZATION PROGRAM IMPLEMENTATION PLAN Revision 0D (Subject to Approval) October 30, 2003 U.S. Department of Energy Carlsbad Field Office DOE/WIPP-02-3214 Table of Contents Acronyms and Abbreviations ..........................................................................................................5 1.0 Introduction..........................................................................................................................6 2.0 Overview of the RH TRU Waste Characterization Program...............................................7 2.1 RH TRU Waste Characterization Overview........................................................... 7 2.2 Data Quality Objectives (DQOs) and Quality Assurance Objectives (QAOs)....... 7 2.2.1 DQO for Defense Waste Determination..................................................................8 2.2.2 DQOs for Radioactive Properties ............................................................................8 2.2.2.1 TRU Waste Determination ................................................................................. 8 2.2.2.2 RH Waste Determination.................................................................................... 9 2.2.2.3 Activity Determination ....................................................................................... 9 2.2.3 DQOs for Physical and Chemical Properties...........................................................9 2.2.3.1 DQO for Residual Liquids...............................................................................
    [Show full text]
  • Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant
    DOE/WIPP-02-3122 TRANSURANIC WASTE ACCEPTANCE CRITERIA FOR THE WASTE ISOLATION PILOT PLANT Revision 6.2 Effective Date: May 30, 2008 U.S. Department of Energy Carlsbad Field Office This document has been submitted as required to: Office of Scientific and Technical Information PO Box 62 Oak Ridge, TN 37831 (865) 576-8401 Additional information about this document may be obtained by calling 1-800-336-9477. Copies may be obtained by contacting the National Technical Information Service, U.S. Department of Commerce, 5285 Port Royal Road, Springfield, VA 22101 DOE/WIPP-02-3122 TRANSURANIC WASTE ACCEPTANCE CRITERIA FOR THE WASTE ISOLATION PILOT PLANT Revision 6.2 Effective Date: May 30, 2008 Approved by: Signature on file Date: 05/27/08 Gary Scott for David C. Moody Carlsbad Field Office Manager Concurred by: Signature on file Date: 05/27/08 Donald C. Gadbury, Director, Office of the National TRU Program iii DOE/WIPP-02-3122 Revision 6.2 Effective Date: May 30, 2008 TABLE OF CONTENTS 1.0 INTRODUCTION ................................................................................................. 1-1 2.0 RESPONSIBILTIES............................................................................................. 2-1 2.1 DOE Headquarters ................................................................................... 2-1 2.2 DOE Carlsbad Field Office (CBFO) .......................................................... 2-1 2.3 DOE Field Elements ................................................................................. 2-2 2.4 TRU Waste
    [Show full text]
  • IMPLEMENTATION GUIDE for Use with DOE M 435.1-1
    IMPLEMENTATION GUIDE for use with DOE M 435.1-1 Chapter III Transuranic Waste Requirements (This page intentionally left blank.) DOE G 435.1-1 III-1 7-09-99 III. A. Definition of Transuranic Waste. Transuranic waste is radioactive waste containing more than 100 nanocuries (3700 becquerels) of alpha-emitting transuranic isotopes per gram of waste, with half-lives greater than 20 years, except for: (1) High-level radioactive waste; (2) Waste that the Secretary of Energy has determined, with the concurrence of the Administrator of the Environmental Protection Agency, does not need the degree of isolation required by the 40 CFR Part 191 disposal regulations; or (3) Waste that the Nuclear Regulatory Commission has approved for disposal on a case-by-case basis in accordance with 10 CFR Part 61. Objective: The objective of this requirement is to provide the criteria for determining if a waste is to be managed in accordance with DOE M 435.1-1, Chapter III, Transuranic Waste Requirements. Additionally, it is necessary to determine if a waste meets the definition of transuranic waste to enable the Department of Energy to comply with provisions in the Waste Isolation Pilot Plant Land Withdrawal Act of 1992, as amended. Discussion: Basis. This definition of transuranic waste is the definition used in the Waste Isolation Pilot Plant (WIPP) Land Withdrawal Act of 1992, as amended. This definition is functionally equivalent to that in 40 CFR Part 191, Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes. The WIPP Land Withdrawal Act of 1992, as amended, defines transuranic waste and limits disposal at WIPP to transuranic waste resulting from atomic energy defense activities which meets this definition.
    [Show full text]
  • Contact-Handled and Remote-Handled Transuranic Waste Packaging
    U.S. Department of Energy NOTICE Washington, D.C. DOE N 435.1 Approved: 8-9-2011 Expires: 8-9-2012 SUBJECT: CONTACT-HANDLED AND REMOTE-HANDLED TRANSURANIC WASTE PACKAGING 1. PURPOSE. This Notice provides specific instructions for packaging and/or repackaging contact-handled transuranic (CH-TRU) and remote-handled transuranic (RH-TRU) waste in a manner consistent with DOE O 435.1, Radioactive Waste Management, DOE M 435.1-1 Chg 1, Radioactive Waste Management Manual, CH-TRU and RH-TRU waste transportation requirements, and Waste Isolation Pilot Plant (WIPP) programmatic requirements. 2. CANCELLATION. None. 3. APPLICABILITY. a. Departmental Applicability. This Notice applies to all Departmental elements when packaging and/or repackaging CH-TRU and RH-TRU waste. This Notice does not apply when CH-TRU and RH-TRU waste are packaged and/or repackaged at a site where the following conditions apply: (1) A WIPP certified program is actively performing CH-TRU and/or RH- TRU waste characterization and certification at that site; and (2) Site personnel responsible for the packaging and/or repackaging operation are receiving feedback on the effectiveness of the packaging and/or repackaging operation from the WIPP certified program. Questions regarding the applicability or implementation of these packaging instructions should be directed to DOE-EM Office of Disposal Operations. The Administrator of the National Nuclear Security Administration will assure that NNSA employees comply with their respective responsibilities under this Notice. Nothing in this Notice will be construed to interfere with the NNSA Administrator’s authority under section 3212(d) of Public Law (P.L.) 106-65 to establish Administration-specific policies, unless disapproved by the Secretary.
    [Show full text]
  • Transuranic Waste Acceptance Criteria for the Waste Isolation Pilot Plant
    DOE/WIPP-02-3122 TRANSURANIC WASTE ACCEPTANCE CRITERIA FOR THE WASTE ISOLATION PILOT PLANT Revision 9 Effective Date: October 18, 2018 This document supersedes DOE/WIPP-02-3122, REV. 8.0 This document implements the WIPP DSA U.S. Department of Energy Carlsbad Field Office This document has been submitted as required to: U.S. Department of Energy Office of Scientific and Technical Information PO Box 62 Oak Ridge, TN 37831 (865) 576-8401 Additional information about this document may be obtained by calling 1-800-336-9477. Unlimited, publicly available full-text scientific and technical reports produced since 1991 are available online at Information Bridge (www.osti.gov/bridge). U.S. Department of Energy and its contractors may obtain full-text reports produced prior to 1991 in paper form, for a processing fee, from: U.S. Department of Energy Office of Scientific and Technical Information P.O. Box 62 Oak Ridge, TN 37831-0062 Phone: (865) 576-8401 Fax: (865) 576-5728 Email: [email protected] Available for sale to the public from: U.S. Department of Commerce National Technical Information Service 5301 Shawnee Rd Alexandria, VA 22312 Phone: (800) 553-6847 or (703) 605-6000 Fax: (703) 605-6900 Email: [email protected] Page 2 of 122 DOE/WIPP-02-3122 TRANSURANIC WASTE ACCEPTANCE CRITERIA FOR THE WASTE ISOLATION PILOT PLANT Revision 9 Effective Date: October 18, 2018 U.S Department of Energy Carlsbad Field Office Approved by: /signature on file/ Date: 10/18/18 Kenneth Princen, Assistant Manager National TRU Program Office Approved by: /signature on file/ Date: 10/18/18 Todd Shrader, Manager Carlsbad Field Office Page 3 of 122 DOE/WIPP-02-3122 Revision 9 Effective Date: October 18, 2018 TABLE OF CONTENTS 1.0 INTRODUCTION ...............................................................................................
    [Show full text]
  • Radioactive and Nonradioactive Waste Intended for Disposal at the Waste Isolation Pilot Plant M G § O L.C
    J~ Radioactive and Nonradioactive Waste Intended for Disposal at the Waste Isolation Pilot Plant m G § O L.C. Sanchez3, P.E. Drezb. J.S. Ratha, H.R. Trellue' fA <=> fH a Sandia National Laboratories, P.O. Box 5800, Albuquerque, NM 87185-0779 USA-;b Drez Environmental Associates, Albuquerque, NM 87111 USA; c Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, NM 87545 Abstract Transuranic (TRU) waste generated by the handling of plutonium in research on or production of U.S. nuclear weapons will be disposed of in the Waste Isolation Pilot Plant (WIPP). This paper describes the physical and radiological properties of the TRU waste that will be deposited in the WIPP. This geologic repository will accommodate up to 175,564 m3 of TRU waste, corresponding to 168,485 m3 of contact-handled (CH-) TRU waste and 7,079 m3 of remote-handled (RH-) TRU waste. Approximately 35% of the TRU waste is currently packaged and stored (i.e., legacy) waste, with the remainder of the waste to be packaged or generated and packaged in activities before the year 2033, the closure time for the repository. These wastes were produced at 27 U.S. Department of Energy (DOE) sites in the course of generating defense nuclear materials. The radionuclide and nonradionuclide inventories for the TRU wastes described in this paper were used in the 1996 WIPP Compliance Certification Application (CCA) performance assessment calculations by Sandia National Laboratories/New Mexico (SNL/NM). Key Words: Compliance certification application (CCA), contact-handled (CH-) transuranic (TRU) waste, containment requirements, performance assessment, radioactive waste, radionuclide inventory, release limits, remote-handled (RH-) TRU, source term, Waste Isolation Pilot Plant, 40 CFR 191.
    [Show full text]
  • Americium-241 It''
    It" • DOE/LLW-130 LP RECEIVE w. NOV 2 1 1995 O SCI $ National Low-Level Waste Management Program 8$ Radionuclide Report Series V-' Volume 14: Americium-241 it'' Nations/ Low-Level Waste Management Program 1 September 1995 ^ m ^^^^mm^^mm^-^n^ EriV DiSTfiiBUTiON OF WIS DOCUMENT IS UHLMTED DOE/LLW-130 National Low-Level Waste Management Program Radionuclide Report Series Volume 14: Americium-241 M. R. Winberg R. S. Garcia Published September 1995 Idaho National Engineering Laboratory Lockheed Idaho Technologies Company Idaho Falls, Idaho 83415 Prepared for the U.S. Department of Energy Assistant Secretary for Environmental Management Under DOE Idaho Operations Office Contract DE-AC07-94ID13223 DISTRIBUTION OF ISIS DOCUMENT 18 UNLBTED ° ' »* DISCLAIMER Portions of this document may be illegible in electronic image products. Images are produced from the best available original document. ABSTRACT This report, Volume 14 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of americium-241 (241Am). This report also includes discussions about waste types and forms in which 241Am can be found and 241Am behavior in the environment and in the human body. DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsi• bility 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.
    [Show full text]
  • Fast Breeder Reactor Programs: History and Status
    Fast Breeder Reactor Programs: 8 History and Status Thomas B. Cochran, Harold A. Feiveson, Walt Patterson, Gennadi Pshakin, M.V. Ramana, Mycle Schneider, Tatsujiro Suzuki, Frank von Hippel A research report of the International Panel on Fissile Materials February 2010 Research Report 8 International Panel on Fissile Materials Fast Breeder Reactor Programs: History and Status Thomas B. Cochran, Harold A. Feiveson, Walt Patterson, Gennadi Pshakin, M.V. Ramana, Mycle Schneider, Tatsujiro Suzuki, Frank von Hippel www.fissilematerials.org February 2010 © 2010 International Panel on Fissile Materials ISBN 978-0-9819275-6-5 This work is licensed under the Creative Commons Attribution-Noncommercial License. To view a copy of this license, visit www.creativecommons.org/licenses/by-nc/3.0 Table of Contents About the IPFM i 1 Overview: The Rise and Fall of Plutonium Breeder Reactors Frank von Hippel 1 2 Fast Breeder Reactors in France Mycle Schneider 17 3 India and Fast Breeder Reactors M. V. Ramana 37 4 Japan’s Plutonium Breeder Reactor and its Fuel Cycle Tatsujiro Suzuki 53 5 The USSR-Russia Fast-Neutron Reactor Program Gennadi Pshakin 63 6 Fast Breeder Reactors in the United Kingdom Walt Patterson 73 7 Fast Reactor Development in the United States Thomas B. Cochran, Harold A. Feiveson, and Frank von Hippel 89 Contributors 113 Fast Breeder Reactor Programs: History and Status Figures Overview: The Rise and Fall of Plutonium Breeder Reactors Figure 1.1 Plutonium breeding. 3 Figure 1.2 History of the price of uranium. 6 Figure 1.3 Funding in OECD countries. 7 Figure 1.4 Dose rate of separated transuranics.
    [Show full text]
  • Final Report
    Annex 6 Acronyms and glossary of technical terms Annex 6 Acronyms and glossary of technical terms Acronyms AGR Advanced Gas-cooled Reactor AWE Atomic Weapons Establishment BE British Energy BNFL British Nuclear Fuels plc BNG British Nuclear Group CORE Cumbrians Against a Radioactive Environment CoWRM Committee on Radioactive Waste Management Defra Department for the Environment, Food and Rural Affairs DTI Department of Trade and Industry HAL High active liquor HEU Highly enriched uranium HLW High level waste IAEA International Atomic Energy Agency ILW Intermediate Level Waste LLW Low level waste LLWR Low Level Waste Repository LMU Liabilities Management Unit LWR Light water reactor MOX Mixed oxide fuel NDA Nuclear Decommissioning Authority NEA/OECD The Nuclear Energy Agency of the Organisation of Economic Cooperation and Development NGO Non-Governmental Organisation NII Nuclear Installations Inspectorate NORM Naturally occurring radioactive materials OCNS Office for Civil Nuclear Security OSPAR OSPAR Convention: The Convention for the Protection of Marine Environment of the North-east Atlantic. PSE Public and stakeholder engagement PWR Pressurised water reactor QA Quality assurance R&D Research and Development RCF Rock characterisation facility RDW Reactor decommissioning waste RSA93 Radioactive Substances Act 1993 RWI Radioactive waste inventory RWMAC Radioactive Waste Management Advisory Committee THORP Thermal oxide reprocessing plant UKAEA United Kingdom Atomic Energy Authority VLLW Very low level waste WIPP Waste Isolation Pilot Plant 186 Managing our radioactive waste safely Annex 6 Acronyms and glossary of technical terms Glossary of technical terms Activity - The number of disintegrations per second which occur in a radioactive source. The unit of activity is the Becquerel. Advanced Gas-cooled Reactor - The reactor type used in the UK's second generation nuclear power plants.
    [Show full text]
  • THE WORLD NUCLEAR WASTE REPORT 2019 Focus Europe. PARTNERS & SPONSORS
    THE WORLD NUCLEAR WASTE REPORT 2019 Focus Europe. PARTNERS & SPONSORS Bürgerinitiative Umweltschutz Lüchow-Dannenberg This report would have not been possible without the generous support of a diverse group of friends and partners, in particular – listed in alphabetical order – the Altner-Combecher Stiftung, Bäuerliche Notgemeinschaft Trebel, Bund für Umwelt und Naturschutz (BUND), Bürgerinitiative Umweltschutz Lüchow-Dannenberg e.V., Climate Core and Green/EFA MEPs Group in the European Parliament, Heinrich-Böll-Stiftung (HBS) and its offices in Berlin, Brussels, Paris, Prague, and Washington DC, KLAR! Schweiz, Annette und Wolf Römmig, and the Swiss Energy Foundation. Thank you all for making this possible! THE WORLD NUCLEAR WASTE REPORT — 2019 3 FOREWORD More than 40 years ago in my home region, the forest near the village of Gorleben was chosen as the location for the German National Nuclear Waste Disposal Center. The site, which is now at the country’s center but at the time was located directly on the border between East and West Germany, was meant to host all facilities for reprocessing, treatment, storage, and a deep geological repository. The company responsible (which has long since closed) intended to open the repository for spent fuel in the salt dome named Gorleben-Rambow in 1999. After Fukushima, the German government decided to phase out nuclear energy for the second time. The experience of the nuclear catastrophe in Japan in 2011 also set in motion the review of the plans for the repository at Gorleben. After around 40 years of debating and fighting over Gorleben, the German government and parliament decided in favor of a new participatory site selection process for the repos- itory for high-level nuclear waste.
    [Show full text]
  • Buried Transuranic-Contaminated Waste Information for US
    BuriedBuried TransuranTransuraniicc-Contaminated-Contaminated WaWasteste InInfoformrmaatiotionn foforr U.S.U.S. DepartmentDepartment ofof EnergyEnergy FacilitiesFacilities JuneJune 20002000 U.S. Department of Energy Office of Environmental Management Buried Transuranic-Contaminated Waste Information for U.S. Department of Energy Facilities June 2000 Table of Contents Abstract ........................................................................... 1 Summary and Results in Context ........................................................ 1 Background ........................................................................ 7 Summary of Data Collection Process .................................................... 9 Inventory of Previously Disposed of TRU-Contaminated Wastes ............................. 11 Buried TRU-Contaminated Wastes .............................................. 11 TRU-Contaminated Wastes Disposed of at Intermediate Depths ....................... 12 Inventory of TRU-Contaminated Soil at the Five Major Sites ................................ 13 TRU-Contaminated Soil Associated with Liquid Discharges .......................... 13 TRU-Contaminated Soil Proximate to Solid Wastes ................................. 14 Additional TRU-Contaminated Waste and Soil ........................................... 15 Risk Estimates for Buried TRU Wastes: Summary of WIPP SEIS II Analysis ................... 16 Buried TRU-Contaminated Waste and Soil Sites Not Addressed in This Report .................. 16 Summary of Buried TRU-Contaminated
    [Show full text]