Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions
Preliminary assessment of accident-tolerant fuels on LWR performance during normal operation and under DB and BDB accident conditions
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DOI：
10.1016/j.jnucmat.2013.09.052
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发表时间：
2014-05-01
影响因子：
3.1
通讯作者：
Wang, D.
中科院分区：
文献类型：
--
作者：
Ott, L. J.;Robb, K. R.;Wang, D.
2011年日本福岛第一核电站发生严重事故后，美国能源部启动了通过开发燃料/包壳来提高轻水反应堆事故耐受性的研究和开发，与标准的二氧化铀/锆合金（Zr）系统相比，可以在相当长的时间段内容忍堆芯中主动冷却的损失，同时在正常操作期间保持或改善燃料性能。分析表明，这些新的候选燃料/包壳材料的燃料性能在正常运行条件下，DB和BDB事故条件下的反应堆系统的影响。(C)2013爱思唯尔有限公司版权所有。
Following the severe accidents at the Japanese Fukushima Daiichi Nuclear Power Station in 2011, the US Department of Energy initiated research and development on the enhancement of the accident tolerance of light water reactors by the development of fuels/cladding that, in comparison with the standard UO2/Zircaloy (Zr) system, can tolerate loss of active cooling in the core for a considerably longer time period while maintaining or improving the fuel performance during normal operations. Analyses are presented that illustrate the impact of these new candidate fuel/cladding materials on the fuel performance at normal operating conditions and on the reactor system under DB and BDB accident conditions. (C) 2013 Elsevier B.V. All rights reserved.