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Fusion neutron streaming benchmark experiments and the analysis by the three-dimensional transport calculation code, tristan

Y. Oka, K. Shin, T. Ida, S. Ohno, S. Sakamoto1989年Fusion Engineering and DesignIF 1.7出版社

AbstractFusion neutron streaming through bent ducts, bent slits, offset slits, and multi-holes in polyethylene shields was measured using TLD, CR-39, and miniature NE213 scintillators. The features of the experiment were the simplicity, and variety of shield geometries, accuracy of hydrogen density of the shield and use of the detectors covering wide energy ranges. The experimental data are very useful for verifying the accuracy of analytical methods. The analysis of the experiment by the three-dimensional TRISTAN code showed very good agreement with the fast neutron responses and fairly good agreement with the responses of the low energy neutrons.

日本語訳

ポリエチレン遮蔽体中の湾曲ダクト、湾曲スリット、オフセットスリット、および多重孔を通る中性子ストリーミングを、TLD、CR-39、および小型NE213シンチレータを用いて測定した。本実験の特徴は、その簡便さ、遮蔽体形状の多様性、遮蔽体の水素密度の正確さ、そして広いエネルギー範囲をカバーする検出器の使用にあった。実験データは、解析手法の精度を検証する上で非常に有用である。三次元コードTRISTANによる実験の解析結果は、高速中性子応答については非常に良い一致を示し、低エネルギー中性子応答についてはかなり良い一致を示した。

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