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Assessement of the JEFF-3.1.1 Neutron Data Library for FOR CSE of LWR Fuel Storage Pools
Edwin Kolbe,Alexander Vasiliev,Hakim Ferroukhi 한국물리학회 2011 THE JOURNAL OF THE KOREAN PHYSICAL SOCIETY Vol.59 No.23
A methodology for criticality safety evaluations (CSE) of light water reactor (LWR) compact storage pools and transport casks based on the Monte Carlo code MCNPX-2.5.0 was recently established at PSI. Validation calculations were performed applying a suite of 15 low-enriched thermal compound uranium and 4 mixed plutonium uranium thermal compound benchmarks extracted from the International Handbook of Evaluated Criticality Safety Benchmark Experiments. In a first part of this paper, the same validation suite, comprising in total 149 benchmark cases, is analyzed with the latest release of the JEFF-3.1.1 nuclear data library. The resulting bias is compared to the ones obtained previously with the ENDF/B-VII.0, JEFF-3.1 and JENDL-3.3 libraries. Secondly, in licensing-related studies for a new PWR commercial wet storage pool, a noticeable sensitivity upon the employed thermal neutron scattering S(α,β) matrix data was observed for water reflected configurations. By performing trend analyses with respect to the magnitude of the thermal flux for a selected subset of benchmark cases, various parameterizations of S(α,β) could be assessed including the one in JEFF-3.1.1. Finally, the benefits from applying several cross-section libraries in CSE will be pointed out.