Analysis of SNEAK-7A and 7B Critical Benchmarks Using 3-D Deterministic Transport with Different Libraries

Conference · Thu Jul 01 04:00:00 EDT 2004

OSTI ID:21160613

Kim, S J ^[1]; Kodeli, I; Sartori, E ^[2]

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1. Korea Atomic Energy Research Institute, Yuseong, Daejeon, 305-353 (Korea, Republic of)
2. OECD NEA Data Bank, 12 Boulevard des Iles, 92130 Issy-les-Moulineaux (France)

Some high-quality reactor physics benchmark experiments are being re-evaluated with today's state-of-the-art methods, particularly using that of detailed 3-D models. Two experiments analysed in the framework of the International Reactor Physics Benchmark Experiments (IRPhE) project are SNEAK-7A and 7B. These assemblies are characterised by Pu-fuelled fast critical assemblies in the Karlsruhe Fast Critical Facility for the purpose of testing the cross section data and calculational methods. As the detailed information on the SNEAK-7A and 7B benchmark experiments becomes available, the purpose of this paper is to neutronically describe these experiments as closely as possible to the configuration as they existed in the critical facility, thereby minimizing subsequent corrections caused by modeling deficiencies. The basic cross section libraries used for this analysis are JEF-2.2 and ENDF/B-VI. Core eigenvalues, spectral indices and central material worths are compared between the predictions and measurements. The capability of modern 3-D transport methods is appreciated and the quality of the basic library is assessed. In addition, the core eigenvalue sensitivity analysis for the basic cross section of each important nuclide is performed, using a sensitivity and uncertainly analysis code. Using the deviation of the calculated spectrum indices from the measurement, together with the sensitivity coefficient, it is shown how the sensitivity analysis can be usefully adopted to figure out a specific detail of a basic cross section needing improvement in each library. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 21160613
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
BENCHMARKS
BORON 7
CONFIGURATION
CORRECTIONS
CROSS SECTIONS
EIGENVALUES
NUCLEAR DATA COLLECTIONS
REACTOR PHYSICS
SENSITIVITY
SENSITIVITY ANALYSIS
ZERO POWER REACTORS