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首页> 外文期刊>Nuclear Engineering and Design >Analysis on split failure of cladding of high burnup BWR rods in reactivity-initiated accident conditions by RANNS code
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Analysis on split failure of cladding of high burnup BWR rods in reactivity-initiated accident conditions by RANNS code

机译:反应性事故条件下高燃耗BWR棒的熔覆层断裂失效的RANNS分析

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摘要

A computer code RANNS was developed to analyze fuel rod behaviors in the reactivity-initiated accident (RIA) conditions. RANNS performs thermal and finite-element mechanical calculation for a single rod in axis-symmetric geometry, where fuel pellet consists of 36 equal-volume ring elements and cladding metallic wall consists of eight equal-thickness ring elements and one outer oxide element. The code can calculate temperature profile inside the rod, contact pressure generated by pellet-clad mechanical interaction (PCMI), stress-strain distribution and their interactions elaborately. An experimental analysis by RANNS begins with pre-test conditions of irradiated rod which are given by the fuel performance code FEMAXI-6. In the present study, analysis was performed on the simulated RIA experiments in the "nuclear safety research reactor" (NSRR), FK-10 and FK-12, with high burnup BWR rods in a cold-start up condition, and stress-strain evolution in the PCMI process was calculated extensively. In the analysis, the pellet-clad bonding was assumed both in the heat conduction and in mechanical restraint. The calculated hoop strain increase was compared with the measured strain gauge data, and satisfactory agreement was obtained. Simulation calculations with broader power pulses anticipated in RIA of commercial BWR were carried out and the resulted cladding hoop stress was compared with the failure stress estimated by comparison of analysis with experimental data.
机译:开发了计算机代码RANNS来分析在反应性事故(RIA)情况下的燃料棒行为。 RANNS对轴对称几何中的单个杆执行热和有限元力学计算,其中燃料芯块由36个等体积的环形元素组成,覆层金属壁由8个等厚度的环形元素和一个外部氧化物元素组成。该代码可以计算杆内的温度曲线,由颗粒包覆的机械相互作用(PCMI)产生的接触压力,应力-应变分布及其相互作用。 RANNS进行的实验分析从辐照杆的测试前条件开始,这些条件由燃料性能代码FEMAXI-6给出。在本研究中,对“核安全研究堆”(NSRR),FK-10和FK-12中的模拟RIA实验进行了分析,其中冷启动条件下的高燃耗BWR棒具有应力应变大量计算了PCMI过程的演变。在分析中,假设在导热和机械约束方面均采用颗粒包覆的结合。将计算出的环向应变增量与测得的应变仪数据进行比较,并获得令人满意的一致性。进行了商用BWR RIA中预期的更宽功率脉冲的仿真计算,并将所得包层环向应力与通过分析与实验数据进行比较而估算的破坏应力进行了比较。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2006年第2期|p.128-139|共12页
  • 作者单位

    Department of Reactor Safety Research, Tokai Research Establishment, Japan Atomic Energy Research Institute, Tokai-mura, Ibaraki-ken 319-1195, Japan;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 原子能技术;
  • 关键词

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