基于活化法及MCNP程序的临界装置功率刻度

Power Confirming for Critical Facility Based on Activation Method and MCNP Code

Reactor Engineering Research Sub-institute, Nuclear Power Institute of China, Chengdu 610041, China

摘要: 介绍了临界装置功率刻度的方法，在不同功率台阶下利用活化法测量临界装置的中子注量率分布及归一点的绝对中子注量率，并利用经修改编译的MCNP程序对临界装置的中子注量率分布进行校核计算。基于中子注量率测量及计算结果通过裂变率法计算不同功率台阶下临界装置的功率，同时外推到堆芯最大热中子注量率为1×10⁸cm^-2•s^-1时的功率，实现了临界装置的功率刻度。
- 中子注量率 ,
- MCNP程序 ,
- 裂变率法 ,
- 功率刻度
Abstract: The method for power confirming was introduced. Neutron fluence rate distribution and absolute neutron fluence rate of one point for critical facility under different powers were measured by activation method. Neutron fluence rate distribution was calculated with compiled MCNP code. The power of critical facility was calculated with fission rate method based on neutron fluence rate. The power was extrapolated while the max thermal neutron fluence rate was 1×10⁸cm^-2•s^-1. The power confirming for critical facility was completed.
- neutron fluence rate ,
- MCNP code ,
- fission rate method ,
- power confirming

[1]	史永谦. 核反应堆中子学实验技术[M]. 北京：原子能出版社，2011：284-285.
[2]	WESTCOTT C H. Effective cross section values for well-moderated thermal reactor spectra, CRRP-960[R]. Chalk River, Canada: Atomic Energy of Canada Ltd., 1960.
[3]	JACKS G M. A study of thermal and resonance neutron flux detectors, DP-608[R]. Aiken: Savannah River Laboratory, 1961.
[4]	BAUMANN N P. Resonance integrals and self-shielding factors for detector foils, DP-817[R]. Aiken: Savannah River Laboratory, 1963.
[5]	邓勇军，李润东，刘永康，等. 确定反应堆核功率刻度中修正系数的新方法[J]. 原子能科学技术，2010, 44(11):1322-1327.DENG Yongjun, LI Rundong, LIU Yongkang, et al. New method in obtaining correction factor of power comfirming[J]. Atomic Energy Science and Technology, 2010, 44（11）: 1322-1327（in Chinese）.
[6]	程品晶，邱蕾，潘佚，等. MCNP源程序修改及应用[J]. 南华大学学报:自然科学版,2007,21(3):97-100.CHENG Pinjing, QIU Lei, PAN Yi, et al. Modification and application of MCNP4c source code[J]. Journal of University of South China: Science and Technology, 2007, 21（3）: 97-100（in Chinese）.