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PHITSコードを用いたHTTR原子炉起動用中性子源の交換作業に伴う遮蔽計算

Shielding calculation by PHITS code during replacement works of startup neutron sources for HTTR operation

篠原 正憲; 石塚 悦男; 島崎 洋祐; 澤畑 洋明

Shinohara, Masanori; Ishitsuka, Etsuo; Shimazaki, Yosuke; Sawahata, Hiroaki

高温工学試験研究炉の起動用中性子源交換作業において、中性子線による作業員の被ばくを低減させるため、燃料交換機遮蔽キャスク下部に仮設中性子遮蔽体を設置した場合の線量当量率をPHITSコードで計算した。この結果、仮設中性子遮蔽体を燃料交換機遮蔽キャスク下部に設置することによって、中性子線による線量当量率を約1桁程度低くできることが明らかとなった。また、実際の交換作業において、仮設中性子遮蔽体を設置した結果、作業員の被ばく積算線量は0.3mSv人となり、前回の0.7mSv人と比較して半減させることができた。

To reduce the neutron exposure dose for workers during the replacement works of the startup neutron sources of the High Temperature Engineering Test Reactor, calculations of the exposure dose in case of temporary neutron shielding at the bottom of fuels handling machine were carried out by the PHITS code. As a result, it is clear that the dose equivalent rate due to neutron radiation can be reduced to about an order of magnitude by setting a temporary neutron shielding at the bottom of shielding cask for the fuel handling machine. In the actual replacement works, by setting temporary neutron shielding, it was achieved that the cumulative equivalent dose of the workers was reduced to 0.3 man mSv which is less than half of cumulative equivalent dose for the previous replacement works; 0.7 man mSv.

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