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Recent Research Activities Using NSRR On Safety Related Issues

机译:最近使用NSRR对安全相关问题的研究活动

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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:本文报告了使用核安全研究反应堆(NSRR)的日本原子能机构(JAEA)对安全相关问题的研究活动的最新进展。 JAEA在2010年推出了阿尔卑斯醛纲领计划,以便获得先进燃料的监管数据。在2011年大东日本地震之后,已经进行了五次新的反应性发起的事故(RIA)对先进燃料的模拟测试。测试的前两个燃料VA-5和VA-6为17×17-PWR型,粘附和再结晶的M-MDA包层,并照射到〜80 GWD / TU。由于颗粒包层机械相互作用,包层失效。此外,在JAEA / IRSN协作的框架中,计划在RIA期间更好地理解裂变气体动力学测试,以更好地了解RIA期间的裂变气体的行为。最近对原型压力传感器的资格测试证明了获得瞬态裂变气体释放历史数据的能力。 JAEA还使用NSRR推出了一个新的实验计划,以调查温度区域超越-DBA基因座的燃油劣化行为。在2014年进行的第一个初步测试证实,NSRR的形状脉冲操作可能能够模拟可能发生超越DBA基因座中的重要现象的高温条件。

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