- AEC Atomic Energy Commission
- AFMS Alternative fuel management scheme
- AHM Auxiliary handling machine
- ALM Auxiliary liquid metal
- ANL Argonne National Laboratory
- ASLB Atomic Safety and Licensing Board
- ATWS Anticipated transients without scram
- BRC Breeder Reactor Corporation
- CAPS Cell area processing system
- CCP Core component pot
- CRBRP Clinch River Breeder Reactor Plant
- CRDM Control rod drive mechanism
- CRIEPI Central Research Institute for the Electric Power Industry (Japan)
- CRM Cost reduction measure
- CRRNM Collapsible rotor-roller nut mechanism
- DBA Design basis accident
- DF Decontamination factor
- DFBR Demonstration Fast Breeder Reactor (Japan)
- DHRS Decay heat removal system, also Direct heat removal service
- DNB Departure from nucleate boiling
- DRACS Direct reactor auxiliary cooling system
- DOE Department of Energy
- EBR Experimental Breeder Reactor
- EM Electromagnetic
- EPRI Electric Power Research Institute
- ERDA Energy Research & Development Administration
- ESF Engineered safety feature
- EVST Ex-vessel storage tank
- EVTM Ex-vessel transfer machine
- ETEC Energy Technology Engineering Center
- FFTF Fast Flux Test Facility
- FHC Fuel handling cell
- GV Guard vessel
- GWe Giga-watt electric
- HCDA Hypothetical core disruptive accident
- HTS Heat transport system
- IAEA International Atomic Energy Authority
- IGRP Inert gas receiving and processing aystem
- IHTS Intermediate heat transport system
- IHX Intermediate heat exchanger
- IRACS Intermediate reactor auxiliary cooling system
- IRP Intermediate rotating plug
- IVTM In-vessel transfer machine
- LMFBR Liquid metal fast breeder reactor
- LMTD Log mean temperature difference
- LRP Large rotating plug
- LRW Liquid radioactive waste
- LOF Loss of flow
- LSPB Large Scale Prototype Breeder
- LWR Light water reactor
- MTHM Metric tonnes heavy metal
- NPSH Net positive suction head
- NRC Nuclear Regulatory Commission
- JAPC Japan Atomic Power Company
- JSFR Japanese Sodium Fast Reactor
- MWD Megawatt days
- MWe Megawatt electric
- MWth Megawatt thermal
- MTU Metric tonnes of uranium
- MTHM Metric tonnes heavy metal
- NSSS Nuclear steam supply system
- OHRS Overflow heat removal system
- OV Overflow vessel
- OVR Open vessel refueling
- PACC Protected air cooled condenser
- PFR Prototype fast reactor (UK)
- PHTS Primary heat transport system
- P&ID Process and instrumentation diagram
- PMC Project Management Corporation
- PNC Power Reactor and Nuclear Fuel Development Corporation (Japan)
- PRA Probabilistic risk assessment
- PRACS Primary reactor auxiliary cooling system
- PRDC Power Reactor Development Company
- PSAR Preliminary safety analysis report
- PSER Preliminary safety evaluation report
- PUREX Plutonium uranium extraction (reprocessing plant)
- PWR Pressurized water reactor
- RAPS Radioactive argon processing system
- RCB Reactor containment building
- RFP Request for proposals
- RFTP Reactor fuel transfer port
- RGT Rotating guide tube
- RDT Reactor Development and Technology (Division of AEC)
- RSB Reactor service building
- RV Reactor vessel
- SCC Standard cubic centimeter
- SEFOR Southwest Experimental Fast Oxide Reactor
- SGAHRS Steam generator auxiliary heat removal system
- SGB Steal generator building
- SGS Steam generating system
- SRE Sodium Reactor Experiment
- SRP Small rotating plug
- SS Stainless steel
- STP Standard temperature and pressure
- SWRPS Sodium water reaction products system
- THDV Thermal hydraulics design value
- TOP Transient overpower
- TRUEX Transuranic extraction (reprocessing plant)
- TWe Terra-watt electric
- UIS Upper internals structure
- WVN Wet vapor nitrogen
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