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拡散計算コードによるHTTRの炉心温度係数算出手法の改良; SRACを用いた温度係数の算出

Improvement of calculation method for temperature coefficient of HTTR by neutronics calculation code based on diffusion theory; Analysis for temperature coefficient by SRAC code system

後藤 実; 高松 邦吉

Goto, Minoru; Takamatsu, Kuniyoshi

動特性計算に用いる炉心の温度係数を、拡散計算コードによるHTTRの炉心計算結果を用い、精度よく計算する手法を検討した。具体的には、炉心の中性子スペクトルをより正確に群定数の作成に反映するために、従来の燃料棒格子モデルに代わり、燃料ブロック格子モデルを格子計算に用いた。燃料ブロック格子モデルを用いた格子計算により群定数を作成し、それを用いた拡散計算コードによるHTTRの炉心計算を行った。その結果から炉心の温度係数を算出し、それをHTTRの動特性計算に用いた。動特性計算の結果は、試験結果に対して良い一致を得ており、動特性計算に用いる炉心の温度係数を高い精度で算出できることを確認した。

The HTTR temperature coefficients required for the core dynamics calculations had been calculated from the HTTR core calculation results by the diffusion code with which the corrections had been performed using the core calculation results by the Monte-Carlo code. Then, the calculation method was improved to obtain the temperature coefficients in which the corrections by the Monte-Carlo code were not required. Specifically, from the point of view of neutron spectrum calculated by lattice calculations, the lattice model was revised which had been used for the calculations of the temperature coefficients. The HTTR core calculations were performed by the diffusion code with the group constants which were generated by the lattice calculations with the revised lattice model. The HTTR core dynamics calculation was performed with the temperature coefficient obtained from the core calculation results. In consequence, the core dynamics calculation result showed good agreement with the experimental data and the valid temperature coefficient could be calculated only by the diffusion code without the corrections by Monte-Carlo code.

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