Solution of a stylized European Pressurized Reactor (EPR) benchmark problem using the coarse mesh radiation transport method (COMET)
Creators
- 1. Nuclear and Radiological Engineering/Medical Physics Programs, Georgia Institute of Technology, Atlanta, Georgia (United States)
Description
In this paper, as additional verification of its accuracy and efficiency, the coarse mesh radiation transport code COMET is compared to Monte Carlo solutions in a stylized benchmark problem based on the European Pressurized Reactor (EPR). The core specifications were taken directly from the Final Safety Analysis Report (FSAR) submitted to the Nuclear Regulatory Commission (NRC) and the reactor was modeled in a stylized manner while maintaining full heterogeneity at the pin and assembly level. Detailed results including assembly eigenvalues, core eigenvalues, and pin fission densities using a 2-group cross section library are presented. COMET results are in excellent agreement with MCNP with eigenvalue relative differences on the order of 10 pcm and average pin fission density relative differences on the order of 1-5%. Some maximum errors were on the order of 10% due to poor statistics on the periphery of the core in the reference results. (author)
Files
Additional details
Identifiers
Publishing Information
- Imprint Title
- Proceedings of the international conference on physics of reactors (PHYSOR2014)
- Imprint Pagination
- 5489 p.
- Journal Page Range
- 14 p.
- Report number
- JAEA-Conf--2014-003
Conference
- Title
- International conference on physics of reactors
- Acronym
- PHYSOR2014
- Dates
- 28 Sep - 3 Oct 2014
- Place
- Kyoto (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 47042803
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; C CODES; CROSS SECTIONS; DATA COVARIANCES; ERRORS; FINITE DIFFERENCE METHOD; FUEL ASSEMBLIES; FUEL PINS; GUIDE TUBES; H CODES; M CODES; MONTE CARLO METHOD; PWR TYPE REACTORS; REACTOR SAFETY; RESPONSE FUNCTIONS; US NRC
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; FUNCTIONS; ITERATIVE METHODS; MATHEMATICAL SOLUTIONS; NATIONAL ORGANIZATIONS; NUMERICAL SOLUTION; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; TUBES; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as CD-ROM Data in PDF format, Folder Name: PAPERS, Paper ID: a11_1106263.pdf; 10 refs., 11 figs., 6 tabs.