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Calculations of safe distance from the point of a severe accident during transportation of a package containing spent nuclear fuels

使用済核燃料輸送物を対象とした過酷事故時での隔離距離の計算

渡辺 文隆 ; 奥野 浩  

Watanabe, Fumitaka; Okuno, Hiroshi

本論文は、核燃料物質輸送の過酷事故に伴う放射性物質放出の影響に関する計算を示す。フランスで用いられている使用済核燃料輸送物TN12を対象とした過酷事故の隔離距離の追計算、「原子力施設等の防災対策について」の追計算、さらに、日本で使用されている使用済核燃料輸送物NFT-14Pを対象に、フランス論文に記された事故想定で計算した。隔離距離の計算結果は30m程度になった。上記の計算は、米国で開発されたHotSpotコードを用いた。日本で開発・利用されているEyesActとの比較計算も行った。

This paper shows our calculations on the effects of a radiological release by assuming a severe accident in nuclear material transportation. Following recalculations of safe distance from the point of a severe accident during transportation of a transportation cask TN12 typically used in France containing spent nuclear fuel, and calculations to replicate the "Regulatory Guide: Emergency Preparedness for Nuclear Facilities", a similar calculation was made for a spent fuel transportation cask NFT-14P that was typically utilized in Japan instead of TN12. The safe distance was calculated to be about 30 m. The above calculations were made with the HotSpot codes which adopted the Gauss plume model and had been developed by the USA. Some additional calculations were made with EyesAct, which was developed and used in Japan, adopting also the Gauss plume model, to compare calculation results.

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