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:
over the fuel rod lifetime. J-6. Higher local power density (Fq) promotes more local FGR. Higher rod average power (Fr), along with a flatter axial power distribution (Fz), promotes more FGR along the fuel stack. Sensitivity cases should be conducted to ensure the limiting fuel rod power history is captured. J-7. Each fuel rod design (e.g., UO2, UO2Gd2O3, part-length, full-length) should be evaluated. J-8. The minimum acceptable number of radial and axial nodes as defined in ANS-5.4 should be used, along with the methodology of summing the release for these nodes, to determine the overall release from the fuel pellets to the fuel void volume. DG-1389, Appendix K, Page K-1 APPENDIX K ACRONYMS ADAMS Agencywide Documents Access and Management System ANSI/ANS American National Standards Institute/American Nuclear Society ARC alternative repair criteria ASME American Society of Mechanical Engineers AST alternative source term BU burnup Bq becquerel BWR boiling-water reactor BWROG Boiling-Water Reactor Owners Group CFR Code of Federal Regulations CEDE committed effective dose equivalent Ci curie CR control room CsI cesium iodide DBA design basis accident DE dose equivalent DF decontamination factor EAB exclusion area boundary ECCS emergency core cooling system EDE effective dose equivalent EDEX effective dose equivalent from external sources EPA U.S. Environmental Protection Agency EQ environmental qualification ESF engineered-safety-feature F Fahrenheit FAST Fuel Analysis Under Steady-State and Transients FF flash fraction FGR fission gas release FSAR final safety analysis report GDC general design criterion/criteria GWd/MTU gigawatt day per metric ton of uranium DG-1389, Appendix K, Page K-2 gpd gallon(s) per day IAEA International Atomic Energy Agency ICRP International Commission 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