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作 者:于稼驷 Yu Jiasi(Ministry of Ecology and Environment of the People’s Republic of China,Beijing 100006,China)
出 处:《核安全》2023年第4期94-106,共13页Nuclear Safety
摘 要:本文介绍了一个较完善的计算铑、钒自给能堆芯中子探测器灵敏度的数学模型,其特点是能计算超热共振中子对铑探测器灵敏度的贡献。同时,提出一个计算铑核素有效中子截面的替代公式,推导出了柱状发射体表面各向同性、均匀面源的穿越该发射体的径迹长度概率函数,并用本文数学模型计算了铑、钒自给能堆芯中子探测器轻水堆灵敏度,与实验结果进行了比较。比较结果表明,本文模型是科学、可行的。In this paper,a perfect mathematical model for calculating the sensitivity of Rh and V self-powered in-core neutron flux detectors is introduced.Its characteristic is that the contribution of epi-thermal resonance neutrons to the sensitivity of Rh detectors is considered.In this paper,an alternative formula for calculating the effective neutron cross section of 103Rh is proposed,and the feasibility and scientificalness of the alternative formula are demonstrated and analyzed.In this paper,the track-length probability function of an isotropic and uniform surface source passing through the cylindrical emitter is given.Using the mathematical model presented in this paper,the sensitivity of the Rhodium and Vanadium self-powered core neutron detectors for light water reactors is calculated and compared with the experimental results.The results show that the model is scientific and feasible.
分 类 号:TL375.4[核科学技术—核技术及应用]
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