铀氢锆瞬态实验装置计算程序的研发

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英文篇名：Research and Development of Computational Code for Uranium-zirconium Hydride Transient Experimental Device 作者：肖启冬 ; 张驰 ; 杨历军 英文作者：XIAO Qidong;ZHANG Chi;YANG Lijun;Division of Reactor Engineering Technology Research,China Institute of Atomic Energy; 关键词：铀氢锆 ; 瞬态计算程序 ; Fuchs-Hansen模型 英文关键词：uranium-zirconium hydride;;transient computational code;;Fuchs-Hansen model 中文刊名：YZJS 英文刊名：Atomic Energy Science and Technology 机构：中国原子能科学研究院反应堆工程技术研究部; 出版日期：2018-07-27 11:01 出版单位：原子能科学技术 年：2018 期：v.52 语种：中文; 页：YZJS201809019 页数：8 CN：09 ISSN：11-2044/TL 分类号：146-153

摘要

本文针对新型核反应堆电源系统物理特性研究的铀氢锆瞬态实验装置,结合点堆动力学方程、非稳态热传导方程和热弹性动力学方程,研发了专用于铀氢锆瞬态实验装置实验过程模拟的瞬态计算程序。以保健物理研究堆(HPRR)为例,利用研发的程序进行模拟,得到HPRR的功率、反应性、温度和径向位移随时间的变化。程序的计算结果与Fuchs-Hansen模型的结果较为一致,验证了该瞬态计算程序的正确性。
        In this paper,the uranium-zirconium hydride transient experimental device was used for the study of the physical characteristics of a new nuclear reactor power system.A new transient computational code was developed,for simulation of the experimental processes of the uranium-zirconium hydride transient experimental device,which was combined point-reactor kinetic equation with heat transfer equation and thermoelastic kinetic equation.Taking Health Physics Research Reactor(HPRR)as an example,the power,reactivity,temperature and radial displacement of HPRR over time were simulated with the developed code.The results of the code are consistent with the results of Fuchs-Hansen model,which verifies the correctness of the transient computational code.

引文

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