Selecting benchmarks for reactor simulations: An application to a lead fast reactor
Creators
- 1. Division of Applied Nuclear Physics, Department of Physics and Astronomy, Uppsala University, Uppsala (Sweden)
- 2. Nuclear Data Section, International Atomic Energy Commission (IAEA), Vienna (Austria)
- 3. Reactor Physics and Systems Behavior Laboratory, Paul Scherrer Institut, 5232 Villigen (Switzerland)
Description
Highlights: • A method is proposed for selecting criticality benchmarks for reactor simulations. • A set of random nuclear data are used to analyze a target application and a set of criticality benchmarks. • Similarity between the target application and benchmark is quantified using a similarity index. • The method has been applied to ELECTRA and a set of plutonium and lead sensitive criticality benchmarks. - Abstract: For several decades reactor design has been supported by computer codes for the investigation of reactor behavior under both steady state and transient conditions. The use of computer codes to simulate reactor behavior enables the investigation of various safety scenarios saving time and cost. There has been an increase in the development of in-house (local) codes by various research groups in recent times for preliminary design of specific or targeted nuclear reactor applications. These codes must be validated and calibrated against experimental benchmark data with their evolution and improvements. Given the large number of benchmarks available, selecting these benchmarks for reactor calculations and validation of simulation codes for specific or target applications can be rather tedious and difficult. In the past, the traditional approach based on expert judgement using information provided in various handbooks, has been used for the selection of these benchmarks. This approach has been criticized because it introduces a user bias into the selection process. This paper presents a method for selecting these benchmarks for reactor calculations for specific reactor applications based on the Total Monte Carlo (TMC) method. First, nuclear model parameters are randomly sampled within a given probability distribution and a large set of random nuclear data files are produced using the TALYS code system. These files are processed and used to analyze a target reactor system and a set of criticality benchmarks. Similarity between the target reactor system and one or several benchmarks is quantified using a similarity index. The method has been applied to the European Lead Cooled Reactor (ELECTRA) and a set of plutonium and lead sensitive criticality benchmarks using the effective multiplication factor (). From the study, strong similarity were observed in the between ELECTRA and some plutonium and lead sensitive criticality benchmarks. Also, for validation purposes, simulation results for a list of selected criticality benchmarks simulated with the MCNPX and SERPENT codes using different nuclear data libraries have been compared with experimentally measured benchmark values.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2016.05.033Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2016.05.033;
- PII
- S0306454916303449;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 96
- Journal Page Range
- p. 158-169
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 50070152
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BENCHMARKS; COMPUTER CODES; CRITICALITY; FAST REACTORS; LEAD COOLED REACTORS; MONTE CARLO METHOD; MULTIPLICATION FACTORS; NUCLEAR DATA COLLECTIONS; NUCLEAR MODELS; PLUTONIUM; PROBABILITY; REACTOR DESIGN; SAFETY; STEADY-STATE CONDITIONS
- Descriptors DEC
- ACTINIDES; CALCULATION METHODS; DESIGN; DIMENSIONLESS NUMBERS; ELEMENTS; EPITHERMAL REACTORS; LIQUID METAL COOLED REACTORS; MATHEMATICAL MODELS; METALS; REACTOR LIFE CYCLE; REACTORS; TRANSURANIUM ELEMENTS
Optional Information
- Copyright
- Copyright (c) 2017 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.