Document: NRC Regulatory Guide
Document ID: 4d46a966-d280-43da-9b03-8b0abe7b29ce
Document Type: regulatory_guide
Title: Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2120/ML21204A065.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.183
CFR Part: 
CFR Title: 

Content:
ommission on Radiological Protection KW/ft kilowatts per foot LHGR linear heat generation rate LOCA loss-of-coolant accident LPZ low population zone LWR light-water reactor μCi/g microcuries per gram m3/s cubic meters per second MHA maximum hypothetical accident MSIV main steam isolation valve MSLB main steamline break NRC U.S. Nuclear Regulatory Commission OMB Office of Management and Budget PRA probabilistic risk assessment PWR pressurized-water reactor R/B release-to-birth RADTRAD RADionuclide, Transport, Removal and Dose Estimation RCS reactor coolant system RG regulatory guide RM radiation monitor scfh standard cubic feet per hour SGTR steam generator tube rupture SRP Standard Review Plan SSC structure, system, and component Sv sievert(s) TEARE total effective aerosol removal efficiency TEDE total effective dose equivalent TID technical information document TR technical report TSC technical support center UFSAR updated final safety analysis report UO2 uranium dioxide