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論文

Behavior of high-burnup advanced LWR fuels under design-basis accident conditions

天谷 政樹; 宇田川 豊; 成川 隆文; 三原 武; 谷口 良徳

Proceedings of 2017 Water Reactor Fuel Performance Meeting (WRFPM 2017) (USB Flash Drive), 10 Pages, 2017/09

JAEA has conducted a research program called ALPS-II program for advanced fuels of LWRs. In this program, the tests simulating a RIA and a LOCA have been performed on the high burnup advanced fuels irradiated in European commercial reactors. The failure limits of the high-burnup advanced fuels under RIA conditions have been obtained by the pulse irradiation tests at the NSRR in JAEA. The information about pellet fragmentation etc. during the pulse irradiations was also obtained from post-test examinations on the test rods after the pulse irradiation tests. As for the simulated LOCA test, integral thermal shock tests and high-temperature oxidation tests have been performed at the RFEF in JAEA. The fracture limits under LOCA and post-LOCA conditions etc. of the high-burnup advanced fuel cladding have been investigated, and it was found that in terms of these materials the fracture boundaries do not decrease and the oxidation does not significantly accelerate in the burnup level examined.

論文

Physical property model for advanced oxide fuels

加藤 正人; McClellan, K.*

Transactions of the American Nuclear Society, 113(1), p.613 - 614, 2015/10

日米協力(CNWG)のもとで先進酸化物燃料に関する共同研究を進めている。共同研究では、サイエンスベース燃料解析コードのためのモデル開発を進めており、本研究は、酸化物燃料の物性モデルに関する報告をする。酸化物燃料の格子定数、熱膨張率、音速の実験データから比熱及び熱伝導率を評価し、実験データとよく一致することを確認した。

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