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Recent Research Activities Using NSRR On Safety Related Issues

机译:使用NSRR在安全相关问题上的近期研究活动

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This paper reports recent progress in the research activities of the Japan Atomic Energy Agency (JAEA) on safety related issues using the Nuclear Safety Research Reactor (NSRR). JAEA launched ALPS-Ⅱ program in 2010 in order to obtain regulatory data for advanced fuels. After the Great East Japan Earthquake in 2011, five new reactivity-initiated accident (RIA) simulated tests on the advanced fuels have been performed. The first two fuels tested, VA-5 and VA-6, were 17×17-PWR-type with stress-relieved and recrystallized M-MDA cladding tube, and irradiated to ~80 GWd/tU. The cladding failed due to the pellet-cladding mechanical interaction. In addition, fission gas dynamics tests to promote a better understanding of the behavior of fission gas during an RIA are planned in the framework of the JAEA/IRSN collaboration. A recent qualification test on a prototype pressure sensor demonstrated its ability to obtain history data of transient fission gas release. JAEA also launched a new experiment program using NSRR to investigate fuel degradation behaviors in the temperature region beyond-DBA LOCAs. The first preliminary test performed in 2014 confirmed that the shaped pulse operation of NSRR may be able to simulate a high temperature condition in which important phenomena in beyond-DBA LOCAs may occur.
机译:本文报告了日本原子能机构(JAEA)使用核安全研究堆(NSRR)在安全相关问题上进行研究的最新进展。为了获得先进燃料的监管数据,JAEA于2010年启动了ALPS-Ⅱ计划。在2011年东日本大地震之后,已经对先进燃料进行了五次新的反应性事故(RIA)模拟试验。测试的前两种燃料VA-5和VA-6为17×17-PWR型,带有应力消除和重结晶的M-MDA包层管,辐照至〜80 GWd / tU。由于颗粒-包层的机械相互作用,导致包层失败。此外,计划在JAEA / IRSN合作的框架内计划进行裂变气体动力学测试,以更好地了解RIA期间的裂变气体行为。最近对原型压力传感器进行的鉴定测试表明,它具有获得瞬变裂变气体释放历史数据的能力。 JAEA还启动了一个使用NSRR的新实验程序,以研究DBA LOCA以外的温度区域内的燃料降解行为。 2014年进行的首次初步测试证实,NSRR的整形脉冲操作可能能够模拟高温条件,在高温条件下,DBA LOCA以外的区域可能会发生重要现象。

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