日本原子力学会和文論文誌
Online ISSN : 2186-2931
Print ISSN : 1347-2879
ISSN-L : 1347-2879
HTTR環状炉心の炉心解析モデルの検討
野尻 直喜半田 雄一島川 聡司後藤 実金子 義彦
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2006 年 5 巻 3 号 p. 241-250

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It was shown from the annular core critical experiment of the HTTR that its excess reactivity values tend to be overestimated about 3%Δk/k by the HTTR core design method. Therefore, assessment of the calculation model for the annular core of the HTTR was systematically undertaken. The revised model was investigated which was based on the SRAC code system.
It was concluded that the multiplication factor of the annular core is considerably affected by the three factors listed below:
(1) The Benoist's anisotropic diffusion coefficients
(2) The mesh interval in the whole core diffusion calculation
(3) The mesh structure of graphite region in fuel lattice cells.
The significantly large discrepancy previously reported was reduced down to 1.6%Δk/k by the revised annular core model.

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© by the Atomic Energy Society of Japan
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