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首页> 外文会议>International congress on advances in nuclear power plants >EXPERIMENTAL VALIDATION OF NUMERICAL METHODS IN A LEBENC CODE FOR SINGLE PHASE NATURAL CIRCULATION MODIFIED FOR A FLUORIDE SALT-COOLED HIGH-TEMPERATURE REACTOR (FHR)
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EXPERIMENTAL VALIDATION OF NUMERICAL METHODS IN A LEBENC CODE FOR SINGLE PHASE NATURAL CIRCULATION MODIFIED FOR A FLUORIDE SALT-COOLED HIGH-TEMPERATURE REACTOR (FHR)

机译：氟化物盐冷却高温反应器（FHR）修正的单相自然循环的Lebenc代码中的数值方法的实验验证

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摘要

The Fluoride salt-cooled High-temperature Reactor (FHR) is a Generation Ⅳ reactor class under consideration by the U.S. Department of Energy which combines many of the strong attributes of alternative reactor technologies. The FHR concept, like many Generation Ⅳ technologies, can respond in a fully passive mode to avoid core damage and subsequent major off site radiation release during severe accidents. Current passive decay heat removal simulation efforts for the FHR have relied on legacy light water reactor codes tuned for high-pressure two-phase flow accident conditions expected during loss of coolant accident scenarios. In this paper we present results from a 1-D single-phase natural circulation code and a validation plan based on the transients encountered in the decay heat removal system of an FHR: loss of heat sink (LOHS), start up flow conditions, and a step change in power. The code, LeBENC, was originally developed by the Bhabha Atomic Research Centre (BARC) to simulate the natural circulation characteristics of lead-bismuth eutectic in a closed rectangular loop. Modifications have been made to the code to make it more suited to the decay heat removal system used in an FHR. An experimental natural circulation loop using the water as a simulant fluid is being built at the University of New Mexico to validate the numerical methods employed in this code. Results from this effort are presented.
机译：氟化盐冷却高温反应堆（FHR）是美国能源部正在考虑的第四代反应堆类别，结合了替代反应堆技术的许多强大特性。像许多第四代技术一样，FHR概念可以以完全被动的方式做出响应，以避免在严重事故期间核心损坏和随后的大量异地辐射释放。当前针对FHR进行的被动衰变除热模拟工作依赖于遗留的轻水堆代码，这些代码针对冷却剂事故场景期间预期发生的高压两相流事故情况进行了调整。在本文中，我们基于一维单相自然循环规范和基于FHR衰减排热系统中遇到的瞬变的验证计划提供了结果：散热片（LOHS），启动流动条件和权力的阶梯式变化。 LeBENC代码最初是由Bhabha原子研究中心（BARC）开发的，用于模拟铅-铋共晶体在闭合矩形环中的自然循环特性。对代码进行了修改，使其更适合FHR中使用的衰减除热系统。新墨西哥大学正在建立一个以水为模拟流体的实验性自然循环回路，以验证该规范中采用的数值方法。展示了这项工作的结果。

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