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Benchmarking MCNP and WIMS/RFSP Against Measurement Data - II: Wolsong Nuclear Power Plant 2

Hangbok Choi, Gyuhong Roh, Donghwan Park

Nuclear Science and Engineering / Volume 150 / Number 1 / Pages 37-55

May 2005

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Benchmark calculations of the Canada deuterium uranium reactor design and analysis codes were performed for the Monte Carlo and conventional methods using Phase-B measurement data of the Wolsong Nuclear Power Plant 2. In this study, the benchmark calculations were done for the criticality, boron worth, reactivity device worth, and flux scan. For the benchmark calculation of the Monte Carlo method by MCNP-4B, the criticality was estimated within 4 mk. The reactivity worth of the control devices was consistent with the measurement data within 15%. For the benchmark calculation of the conventional method composed of WIMS-AECL, SHETAN, and RFSP, the criticality was also predicted within 4 mk. The reactivity device worth was generally consistent with the measured data except for the strong absorbers such as shutoff rods and mechanical control absorbers. The results of the flux distribution calculations were also satisfactory for both code systems.

 
 
 
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