首页> 外文会议>Annual conference of the Canadian Nuclear Society;CNS/CNA student conference >INuclear Data Sensitivity and Uncertainty Analysis for the Canadian Supercritical Water- cooled Reactor (SCWR) 64 - element Fresh Fuel Lattice Cell
【24h】

INuclear Data Sensitivity and Uncertainty Analysis for the Canadian Supercritical Water- cooled Reactor (SCWR) 64 - element Fresh Fuel Lattice Cell

机译:加拿大超临界水冷反应堆(SCAR)64元素新鲜燃料晶格电池的核数据敏感性和不确定性分析

获取原文

摘要

One of the fundamental requirement for any nuclear reactor model isan accurate and complete nuclear data. The Canadian supercritical water-cooled reactor (SCWR) is an advanced GEN-Ⅳ reactor concept for whichoperating conditions and materials differ significantly from conventional reactors in addition to its design complexity illustrated with thehigh-efficiency reentrant channel. Consequently, current nuclear data evaluations may not be suitable for modelling the Canadian SCWR. In this work, a simplified sensitivity and uncertainty analysis of the SCWR-64 elements lattice cell with fresh fuel was investigated at the inlet and the outlet of the channel using TSUNAMI-2D Code which is a part of the SCALE 6.1.3.
机译:任何核反应堆模型的基本要求之一就是准确而完整的核数据。加拿大超临界水冷反应堆(SCWR)是先进的GEN-Ⅳ反应堆概念,其工作条件和材料与常规反应堆明显不同,除了其设计上的复杂性(通过高效折返通道)所说明。因此,当前的核数据评估可能不适用于对加拿大SCWR进行建模。在这项工作中,使用TSALEAMI-2D代码(SCALE 6.1.3的一部分)研究了通道入口和出口处带有新鲜燃料的SCWR-64元素晶格电池的简化灵敏度和不确定性分析。

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