首页> 外文会议>14th International Conference on Nuclear Engineering 2006(ICONE14) vol.3 >PERFORMANCE EVALUATION OF CONTROL SAFETY ROD AND ITS DRIVE MECHANISM OF FAST BREEDER REACTOR DURING SEISMIC EVENT
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PERFORMANCE EVALUATION OF CONTROL SAFETY ROD AND ITS DRIVE MECHANISM OF FAST BREEDER REACTOR DURING SEISMIC EVENT

机译:事件发生过程中快速安全反应堆控制安全杆的性能评价及其驱动机理

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Control and safety rods & their drive mechanisms (CSRDM) and diverse safety rods & their drive mechanisms (DSRDM) are the main constituents of the two independent shutdown systems in Prototype Fast Breeder Reactor (PFBR) of 500 MWe. There are nine CSR and three DSR placed within the hexagonal sheaths, which in turn are located in two radial banks of reactor core. This paper deals with the analysis carried out to predict the performance of CSRDM along with CSR. Analysis is carried out for the static and seismic loading under the fuel handling as well as normal operating conditions with the objective of ensuring structural integrity as well as to estimate the drop time during seismic event. The effects of bowing of sub-assemblies corresponding to the end of life situation have been considered. From the analysis, it is found that the drop time of CSR is 0.82 s, which is less than 1 s, and hence there is no concern of reactor shutdown. Further, it is ensured that there is no mechanical interaction of concern between various parts. The induced stresses are found to be very much less than RCC-MR allowable stress intensity. Thus the performance of CSRDM and CSR is demonstrated to be sound during normal as well as seismic events.
机译:控制和安全棒及其驱动机构(CSRDM)和各种安全棒及其驱动机构(DSRDM)是500 MWe原型快繁反应堆(PFBR)中两个独立停机系统的主要组成部分。在六角形护套中放置了九个CSR和三个DSR,它们依次位于反应堆芯的两个径向排中。本文将进行分析以预测CSRDM和CSR的性能。分析在燃料处理以及正常操作条件下的静态和地震载荷,目的是确保结构完整性以及估计地震事件期间的下降时间。已经考虑了与寿命终止情况相对应的组件弯曲的影响。从分析中发现,CSR的下降时间为0.82s,小于1s,因此无需担心反应堆停工。此外,确保了在各个部分之间没有所关注的机械相互作用。发现感应应力远小于RCC-MR允许的应力强度。因此,在正常以及地震事件中,CSRDM和CSR的性能都得到了证明。

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