Evaluation of large 3600 mwth sodium-cooled fast reactor oecd neutronic benchmarks

L. Buiron*, G. Rimpault, B. Fontaine, T. K. Kim, N. E. Stauff, T. A. Taiwo, A. Yamaji, J. Gulliford, E. Fridmann, I. Pataki, A. Kereszt ri, A. T ta, K. Kugo, K. Sugino, M. M. Uematsu, R. Lin Tan, T. Kozlowski, C. Parisi, A. Ponomarev

*この研究の対応する著者

研究成果: Paper査読

14 被引用数 (Scopus)

抄録

Within the activities of the Working Party on Scientific Issues of Reactor Systems (WPRS) of the OECD, an international collaboration is ongoing on the neutronic analyses of several Generation-IV Sodium-cooled Fast Reactor (SFR) concepts. This paper summarizes the results obtained by participants from institutions of different countries (ANL, CEA, ENEA, HZDR, JAEA, CER, KIT, UIUC) for the large core numerical benchmarks. These results have been obtained using different calculation methods and analysis tools to estimate the core reactivity and isotopic composition evolution, neutronic feedbacks and power distribution. For the different core concepts analyzed, a satisfactory agreement was obtained between participants despite the different calculation schemes used. A good agreement was generally obtained when comparing compositions after burnup, the delayed neutron fraction, the Doppler coefficient, and the sodium void worth. However, some noticeable discrepancies between the k-effective values were observed and are explained in this paper. These are mostly due to the different neutronic libraries employed (JEFF3.1, ENDFB7.0 or JENDL-4.0) and to a lesser extent the calculations methods.

本文言語English
出版ステータスPublished - 2014
外部発表はい
イベント2014 International Conference on Physics of Reactors, PHYSOR 2014 - Kyoto, Japan
継続期間: 2014 9月 282014 10月 3

Conference

Conference2014 International Conference on Physics of Reactors, PHYSOR 2014
国/地域Japan
CityKyoto
Period14/9/2814/10/3

ASJC Scopus subject areas

  • 核物理学および高エネルギー物理学
  • 原子力エネルギーおよび原子力工学

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