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中国科学院核能安全技术研究所 中子输运理论与辐射安全重点实验室 合肥 230031
GAN Quan, male, born in 1988, graduated from University of Science and Technology of China with a doctoral degree in 2016, associate professor, focusing on advanced reactor measurement technology and inversion method
WU Yican, E-mail: yican.wu@fds.org.cn
Received:20 May 2019,
Revised:26 June 2019,
Published:10 September 2019
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甘佺,曹佩,郝丽娟等.基于堆外中子能谱测量的堆芯中子场反演方法[J].核技术,2019,42(09):53-59.
GAN Quan,CAO Pei,HAO Lijuan,et al.An inversion method of in-core neutron field based on ex-core neutron spectrum measurement[J].NUCLEAR TECHNIQUES,2019,42(09):53-59.
甘佺,曹佩,郝丽娟等.基于堆外中子能谱测量的堆芯中子场反演方法[J].核技术,2019,42(09):53-59. DOI: 10.11889/j.0253-3219.2019.hjs.42.090502.
GAN Quan,CAO Pei,HAO Lijuan,et al.An inversion method of in-core neutron field based on ex-core neutron spectrum measurement[J].NUCLEAR TECHNIQUES,2019,42(09):53-59. DOI: 10.11889/j.0253-3219.2019.hjs.42.090502.
目前商用反应堆堆内采用的自给能探测器(Self-Powered Detector,SPD)可以实现堆芯中子通量分布的在线测量,但难以测量中子能谱。同时由于一些先进反应堆堆内服役环境更加恶劣,现有的堆内测量系统难以满足先进反应堆堆芯中子场在线测量的需求。本文提出了一种基于堆外中子能谱测量的堆芯中子场反演方法,通过正向中子输运计算构建堆芯相邻截断面之间的能谱响应矩阵,实现反应堆堆芯中子场的反演计算。通过采用两个简化的反应堆模型进行验证,其中对压力容器处反演的中子能谱与蒙特卡罗输运计算结果平均相对偏差约为14%,在外层燃料组件区域反演的中子能谱与蒙特卡罗输运计算结果平均相对偏差约为11%,初步验证了本方法的可行性。
Background
2
The self-powered detectors (SPD) are widely used in commercial reactor for the real-time measurement of neutron flux distribution
but neutron spectrum cannot be obtained by SPD. Meanwhile
due to the extreme condition of advanced reactor systems
the existing in-core measurement systems cannot meet the requirement of real-time measurement of neutron field in the core of advanced reactor.
Purpose
2
This study aim to develop an inversion method of in-core neutron field based on ex-core neutron spectrum measurement.
Methods
2
First of all
Monte Carlo calculation method was employed to obtain the spectrum response matrix between adjacent truncated planes in the core by forward neutron transport calculation. Then
the in-core neutron field could be inversed. Finally
two simplified reactor models were used for method verification and validation.
Results
2
For the neutron field in the pressure vessel
the average relative deviation between the inversion result and the Monte Carlo transport computation result was about 14%
and for the neutron field in the external fuel region
the average relative deviation was about 11%.
Conclusion
2
The inversion method of in-core neutron field proposed in this paper preliminarily demonstrated the feasibility of the method for neutron spectrum monitoring in the reactor core.
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