首页> 外文期刊>Nuclear Engineering and Design >Research and developments of guidelines for thermal load modeling
【24h】

Research and developments of guidelines for thermal load modeling

机译:热负荷建模准则的研究与开发

获取原文
获取原文并翻译 | 示例
       

摘要

In order to realize reliable and economical plants, Japanese commercialized fast reactors adopt innovative component design such as simplification of a reactor vessel, integration of intermediate heat exchangers with primary pumps, shortening of pipes and reduction of loop numbers. Thermal load, one of the principal loads in fast reactor components, becomes critical in those components. For realistic evaluation and mitigation of thermal loads "Interim Guidelines for Thermal Load Modeling" were developed. These guidelines are referred from "Elevated Temperature Structural Design Guide for Commercialized Fast Reactor (FDS)". Current guidelines deal with system thermal transient load and thermal striping load. As for system thermal transient load, two kinds of modeling method were provided. Concerning thermal striping load, thermal fatigue evaluation method was developed considering attenuation effects of thermal stress related to frequency of temperature fluctuation. Interpretation documents of the guidelines and exemplars of application problems were also provided to support designers.
机译:为了实现可靠和经济的设备,日本商业化的快速反应堆采用了创新的组件设计,例如简化了反应堆容器,将中间热交换器与主泵集成在一起,缩短了管道并减少了回路数量。热负荷是快速反应堆组件中的主要负载之一,在这些组件中变得至关重要。为了现实地评估和减轻热负荷,制定了“热负荷建模临时准则”。这些准则可参考“商业化快速反应器(FDS)的高温结构设计指南”。当前的准则涉及系统热瞬态负载和热剥离负载。对于系统的热瞬态载荷,提供了两种建模方法。关于热剥离负荷,考虑到温度波动频率对热应力的衰减影响,开发了热疲劳评估方法。还提供了指南的解释性文档和应用程序问题的示例以支持设计人员。

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