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LONG TERM MECHANICAL INTEGRITY STUDIES AND RELEASE FROM SPENT FUEL RODS FAILURE

机译:燃料棒故障导致的长期机械完整性研究和缓解

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This paper presents updated results from spent fuelexperimental studies performed at JRC-Karlsruheaddressing handling/transportation and long-termstorage issues. The consequences of potential accidentscausing spent fuel rod failure may involve fuel particlesrelease and dispersion. An impact test using a hammerdrop device and a bending test in hot cell were performedon a spent fuel segment from a UO_2 PWR rod with aburnup of ~67 GWd/tHM. The segments were not defueledand were repressurized to 40 bar before the test. Particlesize distribution analysis of the coarse fraction releasedfrom the rod breakage, which settled by gravity, and ofthe fine fraction, including fuel particles deposited on asecond stage filter of the testing chamber and particlesdeposited on the walls of the impact test chamber and onthe surfaces adjacent the bending setup, were performed.A large number of fine particles (ranging from submicronto >15 micron) was collected especially on thewalls of the impact test chamber. The detailed analysis ofthe results, including fine particle characterization, is stillongoing. The final goal of these investigations is todetermine criteria and conditions governing the responseof spent fuel rods to impact loads and other thermomechanicalsolicitations corresponding to normal and offnormalconditions that may be experienced by the rodduring handling, transportation, storage and afterextended storage. In addition to impact and othermechanical loading tests, property measurements as afunction of accumulated radiation damage are performedon spent fuel and alpha-doped analogues to determine thelong term evolution and the potential effects of ageingprocesses on the mechanical integrity of the spent fuelrod. Spent fuel rod alterations as a function of time andactivity and the alteration kinetics are monitored atmicrostructural level (defects and lattice parameterswelling) and at macroscopic property level (e.g.hardness and thermal conductivity). In order to reproducecumulative damage effects expected after very longstorage time within acceptable laboratory timescales,accelerated damage build-up conditions are applied bytesting unirradiated (U,Pu) oxide with high specificalpha-activity. Data from tailor-made samples arecompared to actual high burnup fuel (UO_2, MOX).
机译:本文介绍了在JRC-Karlsruhe \ r \ n进行的乏燃料\ r \ n实验研究的最新结果,这些研究处理/运输和长期\ r \ n存储问题。潜在事故的后果\ r \ n导致乏燃料棒故障可能涉及燃料颗粒\ r \ n释放和扩散。使用锤子跌落装置进行的冲击试验和在热室中进行的弯曲试验,对没有燃尽的UO_2 PWR棒的乏燃料段进行了试验,燃耗约为67 GWd / tHM。在测试之前,这些段没有加油,并重新加压至40 bar。从杆断裂中释放的粗级颗粒的粒度分布分析,其中重力沉降,细级分包括沉积在测试室第二级过滤器上的燃料颗粒并在撞击测试室的壁上和邻近弯曲装置的表面上沉积了颗粒。\ r \ n大量细颗粒(范围从亚微米\ r \ n到> 15微米)尤其是收集在冲击试验箱的壁上。对结果的详细分析(包括细颗粒表征)仍在进行中。这些研究的最终目标是\ r \ n确定控制乏燃料棒对冲击载荷和其他热机械响应的标准和条件,这些响应与正常和非正常情况相对应。杆\ r \在搬运,运输,存放和以后的存放之后。除了冲击和其他机械载荷测试外,还执行性能测量(作为累积辐射损伤的函数),非乏燃料和掺Al的类似物,以确定长期演化和潜力老化过程对乏燃料机械完整性的影响。在时间上,\ r \ n微观结构水平(缺陷和晶格参数\ r \ nswelling)和宏观性能水平(例如\ r \ n硬度和导热系数)下,监测燃料棒随时间和活性变化的变化动力学。 )。为了在很长的时间内在可接受的实验室时间内再现预期的累积损伤效果,通过测试具有高比重的未辐照(U,Pu)氧化物来施加加速的损伤累积条件\ r \ nalpha活动。将量身定制的样品中的数据与实际高燃耗燃料(UO_2,MOX)进行比较。

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    European Commission, Joint Research Centre (JRC), Directorate for Nuclear Safety and Security, Karlsruhe, Germany vincenzo.rondinella@ec.europa.eu;

    European Commission, Joint Research Centre (JRC), Directorate for Nuclear Safety and Security, Karlsruhe, Germany;

    European Commission, Joint Research Centre (JRC), Directorate for Nuclear Safety and Security, Karlsruhe, Germany;

    European Commission, Joint Research Centre (JRC), Directorate for Nuclear Safety and Security, Karlsruhe, Germany;

    European Commission, Joint Research Centre (JRC), Directorate for Nuclear Safety and Security, Karlsruhe, Germany;

    European Commission, Joint Research Centre (JRC), Directorate for Nuclear Safety and Security, Karlsruhe, Germany;

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