EPRI depletion benchmark calculations using PARAGON
Creators
Description
Highlights: • PARAGON depletion calculations are benchmarked against the EPRI reactivity decrement experiments. • Benchmarks cover a wide range of enrichments, burnups, cooling times, and burnable absorbers, and different depletion and storage conditions. • Results from PARAGON-SCALE scheme are more conservative relative to the benchmark data. • ENDF/B-VII based data reduces the excess conservatism and brings the predictions closer to benchmark reactivity decrement values. - Abstract: In order to conservatively apply burnup credit in spent fuel pool criticality analyses, code validation for both fresh and used fuel is required. Fresh fuel validation is typically done by modeling experiments from the "International Handbook." A depletion validation can determine a bias and bias uncertainty for the worth of the isotopes not found in the fresh fuel critical experiments. Westinghouse's burnup credit methodology uses PARAGON™ (Westinghouse 2-D lattice physics code) and its 70-group cross-section library, which have been benchmarked, qualified, and licensed both as a standalone transport code and as a nuclear data source for core design simulations. A bias and bias uncertainty for the worth of depletion isotopes, however, are not available for PARAGON. Instead, the 5% decrement approach for depletion uncertainty is used, as set forth in the Kopp memo. Recently, EPRI developed a set of benchmarks based on a large set of power distribution measurements to ascertain reactivity biases. The depletion reactivity has been used to create 11 benchmark cases for 10, 20, 30, 40, 50, and 60 GWd/MTU and 3 cooling times 100 h, 5 years, and 15 years. These benchmark cases are analyzed with PARAGON and the SCALE package and sensitivity studies are performed using different cross-section libraries based on ENDF/B-VI.3 and ENDF/B-VII data to assess that the 5% decrement approach is conservative for determining depletion uncertainty
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2015.03.010Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2015.03.010;
- PII
- S0306-4549(15)00143-7;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 81
- Journal Page Range
- p. 1-5
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 47015119
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- BENCHMARKS; BURNABLE POISONS; BURNUP; COOLING TIME; CRITICALITY; ENRICHMENT; EPRI; FUEL STORAGE POOLS; NEUTRON TRANSPORT THEORY; NUCLEAR DATA COLLECTIONS; POWER DISTRIBUTION; REACTIVITY; SENSITIVITY ANALYSIS; SPENT FUEL STORAGE; SPENT FUELS
- Descriptors DEC
- ENERGY SOURCES; FUELS; MATERIALS; NEUTRON ABSORBERS; NUCLEAR FUELS; NUCLEAR POISONS; REACTOR MATERIALS; STORAGE; TRANSPORT THEORY
Optional Information
- Copyright
- Copyright (c) 2015 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.