...
  • 主题
高级搜索  >
历史搜索 清空历史
首页> 外文期刊>Science and technology of nuclear installation >Multiphysical Simulations for the IAEA/ISCP Benchmark Model on the Contact of Pressure Tube and Calandria Tube in the Moderator System of CANDU-6 PHWR
【24h】

Multiphysical Simulations for the IAEA/ISCP Benchmark Model on the Contact of Pressure Tube and Calandria Tube in the Moderator System of CANDU-6 PHWR

机译：CANDU-6 PHWR主持人系统中压力管和尾管接触的IAEA / ISCP基准模型的多物理场模拟

获取原文
获取原文并翻译 | 示例
           
页面导航
  • 摘要
  • 著录项
  • 相似文献
  • 相关主题

摘要

The LOCA (loss of coolant accident) is a kind of severe accident in the operation of PH WR (pressurized heavy water reactor) as well as other nuclear facilities, and possible cause of LOCA can be counted on the ballooning of pressure tube (PT) contacted to the outer calandria tube (CT) in the moderator system of CANDU-6 reactors. In the paper, we simulated the 150-kW experimental facility proposed by IAEA/ISCP, modeling the transient creeping behavior of pressurized tube heated with thermal radiation between the gaps of two concentric pipes. The outer boundary is simplified with a switched model that depends on the local temperature. With a multiphysical model supported by a commercial code, COMSOL multiphysics, the unsteady phenomena are simulated with models concerning various kinds of mechanics such as thermodynamics, nonlinear structural dynamics, and two-phase boiling heat transfer models.
机译：LOCA（冷却剂损失事故）是PH WR（加压重水反应堆）以及其他核设施运行中的一种严重事故，可以通过压力管（PT）的膨胀来计算出LOCA的可能原因。与CANDU-6反应堆减速器系统的外排管（CT）接触。在本文中，我们模拟了IAEA / ISCP提出的150 kW实验设备，模拟了在两个同心管之间的间隙之间受热辐射加热的加压管的瞬态蠕变行为。外部边界通过依赖于本地温度的转换模型得以简化。借助商业代码COMSOL multiphysics支持的多物理模型，可以使用涉及各种力学的模型（例如热力学，非线性结构动力学和两相沸腾传热模型）来模拟非稳态现象。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱：kefu@zhangqiaokeyan.com

京公网安备：11010802029741号 ICP备案号：京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有

  • 客服微信

  • 服务号