首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >ABAQUS analysis of the SiC cladding fuel rod behavior under PWR normal operation conditions
【24h】

ABAQUS analysis of the SiC cladding fuel rod behavior under PWR normal operation conditions

机译:PWR正常运行条件下SiC包层燃料棒行为的ABAQUS分析

获取原文
获取原文并翻译 | 示例
           

摘要

Silicon Carbide (SiC) cladding is anticipated to be superior to zirconium-based cladding with regard to tolerating light water reactor (LWR) accidents, but it is also crucial that the cladding performance under normal operation conditions be well understood. This paper focuses on the modeling of thermomechanical behavior of a two-layer SiC cladding in Pressurized Water Reactor (PWR) fuel rod under normal operation conditions. For this purpose, a set of ABAQUS subroutines has been written to incorporate material properties and behavior models of Chemical Vapor Deposited (CVD) monolithic SiC, Chemical Vapor Infiltration (CVI) SiCf/SiC Ceramic Matrix Composite (CMC) and UO2. Especially, apart from UO2 irradiation behaviors and fuel rod phenomena models (gas pressure, gap heat transfer, etc.) which have been extensively studied, an alternative swelling model of SiC dedicated for transient simulation and a pseudo-ductile behavior model of CVI SiCf/SiC have been implemented. Both models are important for conducting best estimate analysis of the fuel rod in-pile behavior. Then after benchmarking with the BISON fuel performance analysis code, the ABAQUS model is applied to a downscaled PWR fuel rod with two-layer SiC cladding design, considering different cladding thicknesses and covering the conditions of simple constant power levels, power ramps, power operation mode, reactor hot standby and cold shutdown. The effect of swelling differential between CVD SiC and CVI SiCf/SiC is also discussed. With the help of finite element analysis (FEA), the tightly coupled thermomechanical behavior of SiC cladding fuel rod can be well studied. (C) 2018 Elsevier B.V. All rights reserved.
机译:碳化硅(SiC)包覆预计要优于基于锆的包层相对于容忍轻水反应堆(LWR)的事故,但它也是至关重要的是,在正常操作条件下所述包层性能可以很好地理解。本文重点研究的在压水反应堆(PWR)正常操作条件下的燃料条的两层包层的SiC的热机械行为的建模。为了这个目的,一组ABAQUS子程序的已被写入到包括材料特性和化学气相沉积(CVD)单片碳化硅,化学气相渗透(CVI)SICF / SiC陶瓷基复合材料(CMC)和UO2的行为模型。特别是,除了其中已被广泛研究UO2照射行为和燃料棒现象模型(气体压力,间隙的热传递等),溶胀的SiC的模型替代专用于瞬态仿真和CVI SICF的伪延展行为模型/碳化硅已付诸实施。这两款机型都进行该燃料棒堆内行为的最佳估计分析的重要。然后用野牛燃料性能分析代码基准之后,ABAQUS模型应用到一个缩小的PWR燃料杆具有两个层的SiC包层的设计,考虑到不同的包层厚度和覆盖简单恒定功率电平,功率斜坡,功率操作模式的条件,反应器的热待机和冷停堆。肿胀CVD SiC和CVI SICF之间的差分的作用/还讨论的SiC。采用有限元分析(FEA)的帮助下,碳化硅包覆燃料棒的紧密耦合的热机械行为可以被很好地研究。 (c)2018年elestvier b.v.保留所有权利。

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