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軽水炉使用済燃料におけるヨウ素129インベントリの予測精度評価

Evaluation of prediction accuracy of iodine-129 inventory in spent fuel of light water reactor

奥村 啓介; 岡本 力; 小嶋 健介; 羽倉 洋行; 須山 賢也

Okumura, Keisuke; Okamoto, Tsutomu; Kojima, Kensuke; Hagura, Hiroyuki; Suyama, Kenya

長寿命FP核種であるヨウ素129(I-129)について、JENDL-4.0等の最新核データによる核種生成量の予測精度を確認するため、MOSRAシステムの格子燃焼計算モジュール(MOSRA-SRAC)を用いて、美浜3号炉及び海外PWRで得られた使用済燃料の照射後試験解析を行った。その結果、JENDL-4.0やENDF/B-VII.0の核分裂収率を使用すると、I-129の生成量に対する計算値は分析値に比べて約20%の過小評価となり、JNDC/V-2やJEFF-3.1の核分裂収率を用いた方が良い結果(-7%)を与えることがわかった。そこで、照射後試験の分析値に基づく、I-129生成量の簡易評価式を作成した。

In order to confirm the prediction accuracy of I-129 inventory in the nuclear spent fuels of light water reactors, the post irradiation examination analysis was performed for the fuel samples irradiated in a Japanese PWR (Mihama-3) and for the samples irradiated in a foreign PWR, by using recent nuclear data libraries such as JENDL-4.0 and the lattice burnup calculation module of the MOSRA system. As a result, it was found that the fission yield data of JENDL-4.0 and ENDF/B-VII.0 give underestimation of the I-129 inventory by about 20% compared with the assay data. On the other hand, the fission yield data of JNDC/V-2 and JEFF-3.1 give better results although they still give underestiomation (about 7%). Then, we made a simple evaluation formula to predict the I-129 inventory from the assay data.

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