Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors (2023)
Chapter: Appendix C: Acronyms and Abbreviations
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Appendix B: Presentations at the Committee's Information-Gathering Meetings
Appendix C
Next Chapter: Appendix D: Radioactive Waste Classifications and Waste Characteristics from Different Stages of the Fuel Cycle in the United States
Suggested Citation:
"Appendix C: Acronyms and Abbreviations." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press.
doi: 10.17226/26500.
Appendix C
Acronyms and Abbreviations
| ADS | accelerator-driven system |
| AEC | Atomic Energy Commission |
| AFC | Advanced Fuels Campaign |
| AFCI | Advanced Fuel Cycle Initiative |
| AGR | advanced gas reactor |
| AIP | American Institute of Physics |
| AIROX | Atomics International Reduction Oxidation |
| ALWR | advanced light water reactor |
| ANDRA | National Radioactive Waste Management Agency (L’Agence Nationale pour la gestion des Déchets RadioActifs) (France) |
| ANL | Argonne National Laboratory |
| ANS | American Nuclear Society |
| ANSI | American National Standards Institute |
| ARC | Advanced Reactor Concept |
| ARDP | Advanced Reactor Demonstration Program |
| ARPA-E | Advanced Research Projects Agency–Energy |
| ARS | advanced reactor safeguards |
| ASTRID | Advanced Sodium Technological Reactor for Industrial Demonstration |
| ATF | accident-tolerant fuel |
| ATR | Advanced Test Reactor |
| AVR | Arbeitsgemeinschaft Versuchsreaktor (Joint Working Group Experimental Reactor) (Germany) |
| AVR-TLK | dry storage canister (Tritium Laboratory Karlsruhe) (Germany) |
| B205 | Alternative name for Magnox Reprocessing Plant at Sellafield (United Kingdom) |
| BANR | BWXT Advanced Nuclear Reactor |
| BCG | Boston Consulting Group |
| BISO | bistructural isotropic particle fuel |
| BN | fast sodium (reactor) (БН - Быстрый Натриевый) (in Russian abbreviations) |
| BNFL | British Nuclear Fuels Limited |
Suggested Citation:
"Appendix C: Acronyms and Abbreviations." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press.
doi: 10.17226/26500.
| BNL | Brookhaven National Laboratory |
| BRC | 2012 Blue Ribbon Commission on America’s Nuclear Future |
| BREST-OD | Lead-cooled fast reactor—Experimental Demonstration (БРЕСТ-ОД–Быстрый Реактор Естественной безопасности со Свинцовым Теплоносителем—Опытно-Демонстрационный (in Russian abbreviations) |
| BWR | boiling water reactor |
| BWXT | Originally Babcock and Wilcox Technologies |
| C/S | containment and surveillance |
| CANDU | Canadian Deuterium Uranium |
| CARBOWASTE | European Commission’s Carbonaceous Waste program |
| CB&I | CB&I Areva MOX Services, LLC, in 2002, now MOX Services, LLC, formerly known as Chicago Bridge and Ironworks |
| CBO | U.S. Congressional Budget Office |
| CEA | Alternative Energies and Atomic Energy Commission (Commissariat à l’Énergie Atomique et aux Énergies Alternatives) (France) |
| CEFR | China Experimental Fast Reactor |
| CFR | United States Code of Federal Regulations |
| CIGEO | Industrial Centre for Geological Disposal (Centre Industriel de Stockage GEOlogique) (France) |
| CNSC | Canadian Nuclear Safety Commission |
| COEX™ | Co-extraction of uranium and plutonium |
| CORAIL | fuel assembly design contains both LEU and MOX rods (COmbustible Recyclage A ILot) (France) |
| CPF | chemical process facility |
| CPP | chemical processing plant |
| CPPNM | 1979 Convention on the Physical Protection of Nuclear Material (international treaty) and the 2005 Amendment |
| CR | conversion ratio |
| CRBR | Clinch River Breeder Reactor |
| CRS | Congressional Research Service |
| CSA | comprehensive safeguard agreement |
| CTR | CarboThermic Reduction |
| CTR-N | CarboThermic Reduction of uranium oxide followed by Nitridation (synthesis) |
| D&D | decontamination and decommissioning |
| DA | destructive analysis |
| DBT | design basis threat |
| DECON | decontamination (and dismantling) (decommissioning strategy) |
| DIAMEX | diamide extraction |
| DNFSB | Defense Nuclear Facilities Safety Board |
| DNN | Office of Defense Nuclear Nonproliferation (within the U.S. Department of Energy’s National Nuclear Security Administration) |
| DOC | U.S. Department of Commerce |
| DOD | U.S. Department of Defense |
| DOE | U.S. Department of Energy |
| DOE-NE | U.S. Department of Energy’s Office of Nuclear Energy |
| DOS | U.S. Department of State |
| dpa | displacements per atom |
| EBR | experimental breeder reactor |
| EC | European Commission |
Suggested Citation:
"Appendix C: Acronyms and Abbreviations." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press.
doi: 10.17226/26500.
| EDF | Électricité de France, electric utility company |
| EFL | Eligible Facilities List |
| EG | evaluation group (of fuel cycle) |
| Eh | reduction-oxidation (redox) potential versus the standard hydrogen electrode |
| EIA | U.S. Energy Information Administration |
| EIS | Environmental Impact Statement |
| EMT | electrometallurgical treatment |
| ENTOMB | radioactive elements are entombed on site, such as with concrete (decommissioning strategy) |
| EPA | U.S. Environmental Protection Agency |
| EPACT | Energy Policy Act of 2005 |
| EPR | European Pressurized Water Reactor |
| EPRI | Electric Power Research Institute |
| ESA | European Supply Agency |
| EU | enriched uranium |
| eV | electron volt |
| EXAm | EXtraction (recovery) of Americium (process) |
| FBR | fast breeder reactor |
| FBR-MOX | fast breeder reactor-mixed oxide |
| FCCI | fuel-cladding chemical interaction |
| FFH | fusion-fission hybrids |
| FFTF | Fast Flux Test Facility |
| FHR | fluoride-cooled high-temperature reactor |
| fima | fissions per initial metal atom |
| FLiBe | lithium fluoride (LiF) and beryllium fluoride (BeF), includes 2LiF-BeF2 and 7Li2BeF4 |
| FONSI | Finding of No Significant Impact |
| FP | fission product |
| FR | fast reactor |
| FR-MOX | fast reactor-mixed oxide (fuel) |
| FSV | Fort St. Vrain (reactor site) |
| FY | fiscal year |
| GA | General Atomics |
| GAIN | Gateway for Accelerated Innovation in Nuclear |
| GANEX | Grouped ActiNide EXtraction (process) |
| GAO | U.S. Government Accountability Office |
| GE | General Electric |
| GEH | General Electric Hitachi |
| GFR | gas-cooled fast reactor |
| GIF | Generation-IV International Forum |
| GMODS | Glass Material Oxidation and Dissolution System |
| GNEP | Global Nuclear Energy Partnership |
| GRAPA | GRAphite Processing Approaches |
| GSG | IAEA’s General Safety Guide |
| GTCC | Greater than Class C |
| GWd | gigawatt-day |
| GWe | gigawatt electrical |
| Gy | gray |
| H-D-N | hydride-dehydride-nitride (synthesis) |
Suggested Citation:
"Appendix C: Acronyms and Abbreviations." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press.
doi: 10.17226/26500.
| HAC | hypothetical accident conditions |
| HALEU | high-assay low-enriched uranium |
| HDND | high-dose neutron detector |
| HEPA | high efficiency particulate air (filter) |
| HEU | highly enriched uranium |
| HI-STORE | Holtec International-Storage (Consolidated Interim Storage Facility) |
| HLRW | high-level radioactive waste |
| HLW | high-level (radioactive) waste |
| HM | heavy metal |
| HT | high tensile (steel coding) |
| HTGR | high-temperature gas-cooled reactor |
| HTR | high-temperature (gas-cooled) reactor |
| HTR-PM | high-temperature (gas-cooled) reactor—pebble-bed modular |
| I-NERI | International Nuclear Energy Research Initiative |
| IAEA | International Atomic Energy Agency |
| IFR | Integral Fast Reactor |
| ILW | intermediate-level waste |
| IMMONET | IAEA repository for data and reports for irradiated graphite (knowledge network) |
| IMSR | integral molten salt reactor |
| INEPC | Office of International Nuclear Energy Policy and Cooperation (within the U.S. Department of Energy’s Office of Nuclear Energy) |
| INFCIRC | International Atomic Energy Agency’s Information Circular (news communication) |
| INL | Idaho National Laboratory |
| INS | Office of International Nuclear Safeguards (within the U.S. Department of Energy’s National Nuclear Security Administration) |
| IPFM | International Panel on Fissile Materials |
| iPWR | integral pressurized water reactor |
| IPyC | internal pyrolytic carbon |
| ISFSI | Independent Spent Fuel Storage Installation |
| J | joule |
| JAEA | Japan Atomic Energy Agency |
| JCO | Japan Consulting Office, formerly Japan Nuclear Fuel Conversion Co. |
| JNFL | Japan Nuclear Fuel Limited |
| KAERI | Korea Atomic Energy Research Institute |
| KBS | nuclear fuel safety (kärnbränslesäkerhet) (Sweden) |
| keff | effective neutron multiplication factor |
| kgHM | kilogram heavy metal |
| KP-FHR | Kairos Power Fluoride Salt-Cooled High Temperature Reactor |
| KTH | Kungliga Tekniska högskolan (Royal Institute of Technology) (Sweden) |
| ky | kilo years (1,000 years) |
| LANL | Los Alamos National Laboratory |
| LCC | liquid cadmium cathode |
| LCOE | levelized cost of electricity |
| LEU | low-enriched uranium |
| LFR | lead-cooled fast reactor |
| LFTR | liquid fluoride thorium reactor |
Suggested Citation:
"Appendix C: Acronyms and Abbreviations." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press.
doi: 10.17226/26500.
| LLEA | local law enforcement agencies |
| LLFP | long-lived fission products |
| LLNL | Lawrence Livermore National Laboratory |
| LLRW | low-level radioactive waste |
| LLW | low-level (radioactive) waste |
| LWR | light water reactor |
| LWT | legal weight truck (cask) |
| M | mega (as in MCi = megacurie) |
| m3 | cubic meters |
| MA | minor actinides |
| MC&A | material control and accounting |
| MCFR | molten chloride fast reactor |
| MCi | megacurie |
| MCRE | Molten Chloride Reactor Experiment |
| MeV | mega electron volt |
| MFFF | MOX Fuel Fabrication Facility |
| Mg | megagram |
| MIGHTR | modular integrated gas-cooled high temperature reactor |
| MIT | Massachusetts Institute of Technology |
| MOX | mixed oxide |
| MOXEUS | Mixed OXide Enriched Uranium Support, also known as MIX (MIxed oXide [enriched uranium support]) |
| MPACT | Materials Protection, Accounting, and Control Technologies (U.S. Department of Energy campaign) |
| MRIE | maximum routine inspection effort |
| MSR | molten salt reactor |
| MSR-Cl | molten salt reactor—chloride |
| MSR-F | molten salt reactor—fluoride |
| MT | metric ton |
| MTHM | metric tons heavy metal |
| MTU | metric ton of uranium |
| MTW | Honeywell Metropolis Works (conversion plant) |
| MUF | material unaccounted for |
| MWd | megawatt-day |
| MWe | megawatts electric |
| MWh | megawatt hour |
| MWth | megawatts thermal |
| n-stamp | nuclear qualified firm |
| NAC | NAC International, Inc. (formerly Nuclear Assurance Corporation) |
| NAE | National Academy of Engineering |
| NAGRA | National Cooperative for the Disposal of Radioactive Waste (NAtionale Genossenschaft fuer die lagerung Radioaktiver Abfaella) (Switzerland) |
| NASAP | U.S. Department of Energy’s Nonproliferation Alternative Systems Assessment Program |
| NDA | nondestructive assay |
| NEA-OECD | Nuclear Energy Agency of the Organisation for Economic Co-operation and Development |
| NEAC | Nuclear Energy Advisory Committee |
| NED | nuclear explosive device |
| NEI | Nuclear Engineering International |
Suggested Citation:
"Appendix C: Acronyms and Abbreviations." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press.
doi: 10.17226/26500.
| NEICA | Nuclear Energy Innovation Capabilities Act of 2017 |
| NEIMA | Nuclear Energy Innovation and Modernization Act of 2019 |
| NEM | nuclear-explosive material |
| NEXT | New EXtraction system for TRU Recovery (process) |
| NFCE&S | nuclear fuel cycle evaluation and screening |
| NFWG | Nuclear Fuel Working Group |
| NGSAM (red) | Next Generation Systems Analysis Model |
| NHI | Nuclear Hydrogen Initiative |
| NNL | National Nuclear Laboratory |
| NNSA | National Nuclear Security Administration |
| NPM | NuScale Power Module |
| NPR | nuclear power reactor |
| NPT | 1968 Treaty on the Non-Proliferation of Nuclear Weapons |
| NUREG | Nuclear Regulatory Report (U.S. Nuclear Regulatory Commission) |
| NWPA | Nuclear Waste Policy Act of 1982 |
| NWTRB | Nuclear Waste Technical Review Board |
| OECD | Organisation for Economic Co-operation and Development |
| ONWARDS | Optimizing Nuclear Waste and Advanced Reactor Disposal Systems (U.S. Department of Energy’s Advanced Research Project Agency-Energy program) |
| OPyC | outer pyrolytic carbon |
| ORNL | Oak Ridge National Laboratory |
| OTA | Office of Technology Assessment |
| OTC | once-through cycle |
| P&T | partitioning and transmutation |
| PBq | petabecquerel |
| PBR | pebble-bed reactor |
| pH | scale of acidity or alkalinity (base) (potenz hydrogen, respectively) |
| PM | pebble-bed module |
| PPE | personal protective equipment |
| PRISM | Power Reactor Innovative Small Module |
| PUREX | plutonium uranium reduction extraction |
| PWR | pressurized water reactor |
| PyC | pyrolytic carbon |
| Q-brine | quinary salt mine brine |
| R&D | research and development |
| rad | radiation absorbed dose |
| RE | reactive elements (Fe-10Cr-4Al-RE) |
| rem | equivalent dose (Roentgen Equivalent Man [or human]) (predominantly United States) |
| REMIX fuel | REgenerated MIXture of U-Pu oxides |
| RIS | regulatory issue summaries (U.S. Nuclear Regulatory Commission) |
| RRP | Rokkasho Reprocessing Plant (Japan) |
| RT | radiotoxicity |
| S&T | separation and transmutation |
| SAFSTOR | SAFe STORage deferred dismantling (decommissioning strategy) |
| SANEX | Selective ActiNide Extraction |
Suggested Citation:
"Appendix C: Acronyms and Abbreviations." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press.
doi: 10.17226/26500.
| SC-HGTR | Framatome’s Steam-Cooled High-Temperature Gas-Cooled Reactor |
| SCKCEN | StudieCentrum voor Kernenergie·Centre d’Etudes Nucléaire (Belgium) |
| SCWR | supercritical water-cooled reactor |
| SDO | standards developing organization |
| SEALER | SwEdish Advanced LEad Reactor |
| SECY | commission paper (SECretarY of the U.S. Nuclear Regulatory Commission) |
| SFR | sodium-cooled fast reactor |
| SISUS | Subgroup on IAEA Safeguards in the United States |
| SMR | small modular reactor |
| SNF/HLW | spent nuclear fuel and high-level radioactive waste |
| SNL | Sandia National Laboratories |
| SNM | special nuclear materials |
| SQ | significant quantities (of special nuclear materials) |
| SRS | Savannah River Site |
| SSAC | State System of Accounting for and Control (of nuclear material) |
| SSNM | strategic special nuclear materials |
| SSR-W | stable salt reactor—wasteburner |
| STATS report | acronym for separations technology and transmutation systems, the 1996 National Research Council report, Nuclear Wastes: Technologies for Separations and Transmutation |
| SUBATECH | Subatomic Physics and Associated Technologies (Laboratoire de Physique SUBAtomique et des TECHnologies Associées) (France) |
| Sv | Sieverts |
| SVBR | Lead-Bismuth Fast Reactor (SVBR—Свинцово-Висмутовый Быстрый Реактор) (in Russian abbreviations) |
| SWU | separative work unit |
| t1/2 | half-life (of a radioactive substance) |
| TALSPEAK | Trivalent Actinide Lanthanide Separation with Phosphorus-reagent Extraction from Aqueous Komplexes |
| TBP | tributyl phosphate |
| TBq | terabecquerel |
| TECDOC | International Atomic Energy Agency’s TEChnical DOCument |
| TENEX | uranium products supplier (Techsnabexport (Техснабэкспорт) (Russia) |
| THORP | THermal Oxide Reprocessing Plant |
| TRISO | TRistructural ISOtropic |
| TRL | technical readiness level |
| TRU | transuranic elements |
| TRUEX | TRansUranium Extraction (process) |
| U3O8 | triuranium octoxide |
| UC | uranium carbide |
| UCO | uranium oxycarbide |
| Udep | depleted uranium |
| UF6 | uranium hexafluoride |
| UK | United Kingdom |
| UN | United Nations |
| UNF | used nuclear fuel |
| UO2 | uranium dioxide |
| UOX | uranium oxide |
| Urep | reprocessed uranium |
Suggested Citation:
"Appendix C: Acronyms and Abbreviations." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press.
doi: 10.17226/26500.
| UREX | uranium recovery by extraction |
| U.S. NRC | U.S. Nuclear Regulatory Commission |
| U.S.C. | United States Code of Law |
| VHTR | very high-temperature reactor |
| VOA | voluntary offer agreement |
| VTR | versatile test reactor |
| W/THM | watts per ton of heavy metal |
| WIPP | Waste Isolation Pilot Plant |
| WNA | World Nuclear Association |
| WNN | World Nuclear News |
| WTP | Waste Treatment Plant |
| WVDP | West Valley Demonstration Project |
Suggested Citation:
"Appendix C: Acronyms and Abbreviations." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press.
doi: 10.17226/26500.
Suggested Citation:
"Appendix C: Acronyms and Abbreviations." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press.
doi: 10.17226/26500.
Suggested Citation:
"Appendix C: Acronyms and Abbreviations." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press.
doi: 10.17226/26500.
Suggested Citation:
"Appendix C: Acronyms and Abbreviations." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press.
doi: 10.17226/26500.
Suggested Citation:
"Appendix C: Acronyms and Abbreviations." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press.
doi: 10.17226/26500.
Suggested Citation:
"Appendix C: Acronyms and Abbreviations." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press.
doi: 10.17226/26500.
Suggested Citation:
"Appendix C: Acronyms and Abbreviations." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press.
doi: 10.17226/26500.
Suggested Citation:
"Appendix C: Acronyms and Abbreviations." National Academies of Sciences, Engineering, and Medicine. 2023. Merits and Viability of Different Nuclear Fuel Cycles and Technology Options and the Waste Aspects of Advanced Nuclear Reactors. Washington, DC: The National Academies Press.
doi: 10.17226/26500.
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