中国实验快堆反应性温度系数理论分析和试验研究  被引量:1

Measurement and Analysis of Reactivity Temperature Coefficient of CEFR

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作  者:陈仪煜[1] 胡赟[1] 杨晓燕[1] 范振东[1] 张强[1] 赵金坤[1] 李泽华[1] 

机构地区:[1]中国原子能科学研究院中国实验快堆工程部,北京102413

出  处:《原子能科学技术》2013年第B06期88-91,共4页Atomic Energy Science and Technology

摘  要:利用CITATION程序对中国实验快堆(CEFR)反应性温度系数进行计算,同时与其他程序计算结果和实验测量值进行比较。CEFR反应性温度系数约为-4pcm/℃,计算结果与实验值吻合较好。升温和降温过程的反应性温度系数测量误差约为11%,满足试验验收准则。测量结果可校核理论计算结果,同时为CEFR的安全运行和在换料情况下的反应性平衡分析提供参考数据。The reactivity temperature coefficient of CEFR was calculated by CITATION program and compared with the results calculated by correlative programs and measured from experiments for temperature effects.It is indicated that the calculation results from CITATION agree well with measured values.The reactivity temperature coefficient of CEFR is about-4 pcm/℃.The deviation of the measured values between the temperature increasing and decreasing processes is about 11%,which satisfies the experiment acceptance criteria.The measured results can validate the calculation ones by program and can provide important reference data for the safety operation of CEFR and the analysis of the reactivity balance in the reactor refueling situation.

关 键 词:中国实验快堆 反应性温度效应 反应性温度系数 CITATION程序 

分 类 号:TL326[核科学技术—核技术及应用]

 

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