• 主题
高级搜索  >
历史搜索 清空历史
首页> 外文会议>International conference on nuclear engineering;ASME power conference >COMPARATIVE STUDY IN THE STABILITY ANALYSIS CODE OF LAPUR5.2 AND LAPUR6.0 FOR THE KUOSHENG NPP
【24h】

COMPARATIVE STUDY IN THE STABILITY ANALYSIS CODE OF LAPUR5.2 AND LAPUR6.0 FOR THE KUOSHENG NPP

机译：国民党核电厂LAPUR5.2和LAPUR6.0稳定性分析代码的比较研究

获取原文
页面导航
  • 摘要
  • 著录项
  • 相似文献
  • 相关主题

摘要

Under certain conditions, boiling water reactors (BWRs) would be susceptible to couple neutron-thermalhydraulic instability. It is important to predict such potential problems as early as possible and prevent the core instability from happening. In each BWR reload core design, fuel vendors are required to provide instability boundaries on power/flow map to assure safety operation of the nuclear reactor. In Taiwan, a LAPUR5.2 methodology had been adapted to build up the remarkable analysis mode for different types BWRs to verify vendor's results. However, with upgrading nuclear safety technology, most of boiling water reactors has been adopting partial length fuel assemblies to reduce two-phase pressure drop and void fraction, to improve reactor stability. The question is that LAPUR5.2 methodology cannot precisely analysis stability characteristics from the variation of flow area in fuel assemblies. From the reasons of upgrading stability analysis, a LAPUR6.0 methodology had built to do the related researches. This research was based on a comparison study between LAPUR5.2 and LAPUR6.0 to realize the major differences and their effects on stability characteristics. According to the comparison results for Kuosheng Nuclear Power Plant Unit 2 Cycle 21 reload design, it shows that LAPUR6.0 can completely present pressure drop, void fraction and density reactivity coefficient from the changing of flow area and fuel spacers.
机译：在某些条件下，沸水反应堆（BWR）容易受到中子-热工水力不稳定的耦合。重要的是尽早预测此类潜在问题，并防止发生核心不稳定性。在每个BWR重装堆芯设计中，要求燃料供应商在功率/流量图上提供不稳定边界，以确保核反应堆的安全运行。在台湾，已对LAPUR5.2方法进行了调整，以针对不同类型的BWR建立出色的分析模式，以验证供应商的结果。但是，随着核安全技术的升级，大多数沸水反应堆都采用了部分长度的燃料组件来减少两相压降和空隙率，以提高反应堆的稳定性。问题在于，LAPUR5.2方法不能从燃料组件中流通面积的变化中准确地分析稳定性特征。从升级稳定性分析的原因出发，建立了LAPUR6.0方法进行相关研究。本研究基于LAPUR5.2和LAPUR6.0之间的比较研究，以了解主要差异及其对稳定性特征的影响。根据国升核电厂2号机组21周期重载设计的比较结果，可知LAPUR6.0可以通过改变流动面积和燃料隔板，完全表现出压降，空隙率和密度反应系数。

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