Nomenclature

a/o atom percent ABR Actinide Burner Reactor

ADS Accelerator Driven System AFCI Advanced Fuel Cycle Initiative ALMR Advanced Liquid Metal-cooled Reactor ALWR Advanced Light Water Reactor An actinides

APA Advanced Plutonium Assembly ATW Accelerator Transmutation of Waste

BOC Beginning of Cycle BOL Beginning of Life BOP Balance of Plant

BP Burnable Poison

BW boron reactivity worth BWR Boiling Water Reactor CANDU Canada Deutrium Uranium reactor

CERCER ceramic fuel particle dispersed in a ceramic matrix CERMET ceramic fuel particle dispersed in a metallic matrix CF Capacity Factor CHF Critical Heat Flux

CMS Core Management System COE Cost of Electricity CONFU Combined Non-Fertile and UO2 assembly CR Conversion Ratio

CZP Cold Zero Power

D&D Decommissioning and Decontamination DDC Distributed Doppler Coefficient DNBR Departure from Nucleate Boiling Ratio EFPD Effective Full Power Day EFPY Effective Full Power Year

EOC End of Cycle EOL End of Life

FBR Fast Breeder Reactor

FCC Fuel Cycle Cost FFF Fertile free fuel

FP fission product FTC Fuel Temperature Coefficient GT-MHR Gas Turbine-Modular Helium Reactor

H/HM Hydrogen to Heavy Metal Atom Ratio HFP Hot Full Power

HLW High-Level Waste HM Heavy Metal HTGR High Temperature Gas-cooled Reactor HZP Hot Zero Power

IFBA Integrated Fuel Burnable Absorber IFR Integral Fast Reactor IHM Initial Heavy Metal LLFP Long lived fission products LMFBR Liquid Metal Fast Breeder Reactor Ln Lanthanides

LOCA Loss of Coolant Accident

LOFA Loss of Flow Accident

LRM Linear Reactivity Model LWR Light Water Reactor MA Minor actinides

MCNP Monte Carlo N-Particle Transport Code MCODE MCNP-ORIGEN DEpletion Program MDNBR Minimum Departure from Nucleate Boiling Ratio METMET Metallic fuel in metallic matrix

MOX Mixed Oxide (UO2 and PuO2) fuel MTC Moderator Temperature Coefficient MTIHM Metric Ton Initial Heavy Metal MWd/kgIHM MWd per kg IHM, equivalent to GWD per MTIHM NFC Nuclear Fuel Cycle NU Natural Uranium

O&M Operation and Maintenance

ORIGEN Oak Ridge Isotope GENeration and Depletion Code PCI Pellet-Cladding Interaction pcm percent milli ρ, (10-5 ∆k/k) ppm part per million PUREX Pu-U recovery by extraction process PWR Pressurized Water Reactor

R&D Research and Development RCCA Rod Cluster Control Assembly REA Rod Ejection Accident RG Pu Reactor Grade Plutonium

RIA Reactivity initiated accident SF Spontaneous Fission SLFP Short lived fission products SSP Solid solution pellet (homogeneous) SWU Separative Work Unit TBP Tri-butyl phosphate TRU Trans-uranic elements

TRUEX Trans-uranic elements recovery by extraction process UREX Uranium recovery by extraction process v/o volume percent VIPRE Versatile Internals and Component Program for Reactors; EPRI Vm/Vf Moderator to Fuel volume ratio

w/o weight percent WG Pu Weapon Grade Plutonium