Analysis of SHE critical experiments by neutronic design codes for experimental very high temperature reactor.

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概要

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• Analyses have been performed on various experiments conducted using the Semi-Homo-geneous Experimental Assembly (SHE) to examine the accuracy of computer codes employed in the neutronic design of experimental Very High Temperature Reactor (VHTR). The neu-tronic design codes are DELIGHT-6 to obtain the neutron spectrum of a fuel cell and to produce group constants with burnup utilizing the nuclear data from ENDF-B/IV, CITDEGA to calculate the three-dimensional core performance considering the coupling effect between neutronic and thermohydraulic characteristics, and ANISN-JR and TWOTRAN-II for transport calcula-tion. These codes are examined by the analysis on the integral quantities of effective multi-plication factor, neutron flux distribution, burnable poison rod worth and control rod worth. The maximum degrees of disagreement with the relevant experiments are 0.57, 5, 7 and 5%, respectively.

• 一般社団法人 日本原子力学会の論文

著者

• Hirano Mitsumasa

  Japan Nuclear Energy Safety Organization

• TAKANO Makoto

  Japan Atomic Energy Research Institute

• DOI Takeshi

  Japan Atomic Energy Research Institute

• SHINDO Ryuiti

  Japan Atomic Energy Research Institute

• HIRANO Mitsumasa

  Japan Atomic Energy Research Institute

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