Standardized verification of fuel cycle modeling
Creators
- 1. Argonne National Laboratory (United States)
- 2. Idaho National Laboratory (United States)
- 3. Oak Ridge National Laboratory (United States)
- 4. Brookhaven National Laboratory (United States)
- 5. National Nuclear Laboratory (United Kingdom)
Description
Highlights: • Iterative verification for fuel cycle codes and spreadsheets. • Strict level of agreement. - Abstract: A nuclear fuel cycle systems modeling and code-to-code comparison effort was coordinated across multiple national laboratories to verify the tools needed to perform fuel cycle analyses of the transition from a once-through nuclear fuel cycle to a sustainable potential future fuel cycle. For this verification study, a simplified example transition scenario was developed to serve as a test case for the four systems codes involved (DYMOND, VISION, ORION, and MARKAL), each used by a different laboratory participant. In addition, all participants produced spreadsheet solutions for the test case to check all the mass flows and reactor/facility profiles on a year-by-year basis throughout the simulation period. The test case specifications describe a transition from the current US fleet of light water reactors to a future fleet of sodium-cooled fast reactors that continuously recycle transuranic elements as fuel. After several initial coordinated modeling and calculation attempts, it was revealed that most of the differences in code results were not due to different code algorithms or calculation approaches, but due to different interpretations of the input specifications among the analysts. Therefore, the specifications for the test case itself were iteratively updated to remove ambiguity and to help calibrate interpretations. In addition, a few corrections and modifications were made to the codes as well, which led to excellent agreement between all codes and spreadsheets for this test case. Although no fuel cycle transition analysis codes matched the spreadsheet results exactly, all remaining differences in the results were due to fundamental differences in code structure and/or were thoroughly explained. The specifications and example results are provided so that they can be used to verify additional codes in the future for such fuel cycle transition scenarios.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2016.03.002Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2016.03.002;
- PII
- S0306-4549(16)30109-8;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 94
- Journal Page Range
- p. 300-312
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 47125263
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ALGORITHMS; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; CORRECTIONS; D CODES; FUEL CYCLE; ITERATIVE METHODS; M CODES; MATHEMATICAL SOLUTIONS; MODIFICATIONS; NUCLEAR FUELS; SODIUM COOLED REACTORS; SPECIFICATIONS; V CODES; VERIFICATION; WATER COOLED REACTORS; WATER MODERATED REACTORS
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; ENERGY SOURCES; EVALUATION; FUELS; LIQUID METAL COOLED REACTORS; MATERIALS; MATHEMATICAL LOGIC; REACTOR MATERIALS; REACTORS; SIMULATION
Optional Information
- Copyright
- Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.