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HTR-10一回路流量变化试验的模拟
引用本文:陈福冰,董玉杰,张作义,郑艳华,石磊,李富.HTR-10一回路流量变化试验的模拟[J].核科学与工程,2017,37(2).
作者姓名:陈福冰  董玉杰  张作义  郑艳华  石磊  李富
作者单位:清华大学核能与新能源技术研究院,先进核能技术协同创新中心, 先进反应堆工程与安全教育部重点实验室,北京100084
基金项目:国家重大科技专项经费资助项目
摘    要:10 MW高温气冷实验堆(HTR-10)是我国第一座高温气冷堆。一回路流量变化试验是HTR-10的三个动态特性试验之一,该试验不仅证明了反应堆的功率自调节性能,也为系统分析程序的验证提供了实测数据。基于实际的试验工况,利用THERMIX程序对一回路流量变化试验进行了模拟,分析了反应堆主要参数的变化。关于反应堆功率,计算结果与试验结果符合得很好,证明程序能够满意地再现HTR-10在该试验中的动态特性。试验过程中,燃料元件中心最高温度始终低于1 230℃的温度限值。

关 键 词:10MW高温气冷实验堆  一回路流量变化试验  THERMIX  程序验证

Simulation of the HTR-10Primary Mass Flow Variation Test
CHEN Fu-bing,DONG Yu-jie,ZHANG Zuo-yi,ZHENG Yan-hua,SHI Lei,LI Fu.Simulation of the HTR-10Primary Mass Flow Variation Test[J].Chinese Journal of Nuclear Science and Engineering,2017,37(2).
Authors:CHEN Fu-bing  DONG Yu-jie  ZHANG Zuo-yi  ZHENG Yan-hua  SHI Lei  LI Fu
Abstract:The 10 MW high temperature gas-cooled reactor (HTR-10) is the first of its kind in China. The primary mass flow variation test is one of the three dynamic characteristic tests conducted on HTR-10. This test not only verifies the HTR-10 reactor power self-adjustment capability, but also provides measured data for the validation of system analysis codes. Based on actual test conditions, the primary mass flow variation test is simulated using the THERMIX code. Furthermore, main reactor parameters of interest are analyzed. The calculated reactor power agrees well with the test one, demonstrating that the HTR-10 dynamic characteristics can be reproduced satisfactorily by THERMIX. During the test process, the maximum fuel center temperature is always below its limit value of 1 230 ℃.
Keywords:10 MW high temperature gas-cooled reactor  Primary mass flow variation test  THERMIX  Code validation
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