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首页> 外文期刊>Nuclear Engineering and Design >Numerical simulation of three-dimensional thermal-hydraulic behavior for HTTR (High Temperature Engineering Test Reactor)
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Numerical simulation of three-dimensional thermal-hydraulic behavior for HTTR (High Temperature Engineering Test Reactor)

机译:HTTR(高温工程试验堆)三维热工行为的数值模拟

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摘要

Safety demonstration tests using the HTTR (High Temperature Engineering Test Reactor) are now in progress in order to verify the inherent safety features and to improve safety designing and analysis technologies for future HTGR (high temperature gas-cooled reactor). Coolant flow reduction test is one of the safety demonstration tests for the purpose of demonstration of inherent HTGR safety features in the case that coolant flow is reduced by tripping of helium gas circulators. If reactor core element temperature and core internal structure temperature during abnormal events are estimated by numerical simulation with high-accuracy, developed numerical simulation method can be applied to future HTGR designing efficiently. In the present research, three-dimensional in- and ex-vessel thermal-hydraulic calculations for the HTTR are performed with a commercially available thermal-hydraulic analysis code "STAR-CD(r)" with finite volume method. The calculations are performed for normal operation and coolant flow reduction tests of the HTTR. Then calculated temperatures are compared with measured ones obtained in normal operation and coolant flow reduction test. As the result, calculated temperatures are good agreement with measured ones in normal operation and coolant flow reduction test.
机译:目前正在进行使用HTTR(高温工程测试反应堆)的安全演示测试,以验证其固有的安全特性并改善未来HTGR(高温气冷堆)的安全设计和分析技术。冷却液流量减少测试是一项安全演示测试,目的是演示固有的HTGR安全功能,以防氦气循环器跳闸降低冷却液流量。如果通过高精度的数值模拟来估算异常事件期间反应堆堆芯元件温度和堆芯内部结构温度,则可以将开发的数值模拟方法有效地应用于未来的高温气冷堆设计。在本研究中,使用有限体积法使用市售的热工分析代码“ STAR-CD(r)”执行HTTR的三维船内热工计算。计算是针对HTTR的正常运行和冷却液流量减少测试进行的。然后将计算出的温度与正常运行和冷却液流量减少测试中获得的测得温度进行比较。结果,计算出的温度与正常运行和冷却液流量减少测试中测得的温度吻合良好。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2011年第5期|p.1616-1626|共11页
  • 作者单位

    Department of HTTR, Oarai Research and Development Center, Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Higashi-lbaraki-gun, Ibaraki-ken 31 l-1394,Japan;

    Department of HTTR, Oarai Research and Development Center, Japan Atomic Energy Agency, 4002 Narita-cho, Oarai-machi, Higashi-lbaraki-gun, Ibaraki-ken 31 l-1394,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
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