Development and Application of Control Rod Drive Mechanism Expansion Reactivity Feedback Model

Zhang Xisi; Yang Peng; Xue Fangyuan; Huo Xingkai; Liu Yizhe

doi:10.13832/j.jnpe.2023.03.0165

Volume 44 Issue 3

Jun. 2023

Turn off MathJax

Article Contents

Article Navigation > Nuclear Power Engineering > 2023 > 44(3): 165-168

Zhang Xisi, Yang Peng, Xue Fangyuan, Huo Xingkai, Liu Yizhe. Development and Application of Control Rod Drive Mechanism Expansion Reactivity Feedback Model[J]. Nuclear Power Engineering, 2023, 44(3): 165-168. doi: 10.13832/j.jnpe.2023.03.0165

Citation:

Zhang Xisi, Yang Peng, Xue Fangyuan, Huo Xingkai, Liu Yizhe. Development and Application of Control Rod Drive Mechanism Expansion Reactivity Feedback Model[J]. Nuclear Power Engineering, 2023, 44(3): 165-168. doi: 10.13832/j.jnpe.2023.03.0165

Citation:

PDF( 2745 KB)

Development and Application of Control Rod Drive Mechanism Expansion Reactivity Feedback Model

doi: 10.13832/j.jnpe.2023.03.0165

1.
China Institute of Atomic Energy, Beijing, 102413, China
2.
China Institute of Nuclear Industry Strategy, Beijing, 100048, China

Received Date: 2022-07-02
Rev Recd Date: 2022-08-12
Publish Date: 2023-06-15

Abstract

Abstract

In the power test phase of China Experimental Fast Reactor, the power reactivity measurement test was carried out. The results showed that there was a large deviation between the measured values and the theoretical calculation values, and the calculation method of power reactivity needed to be improved. This research analyzed the deviation between the theoretical calculation values and the measured values of China Experimental Fast Reactor power reactivity, and the cause of the deviation was found out. Furthermore, this research developed a control rod drive mechanism expansion reactivity feedback model to correct the theoretical calculation results. The results show that the corrected theoretical calculation values are in good agreement with the measured values, with a relative error of 6.5%. Therefore, the control rod drive mechanism expansion reactivity feedback model developed in this research can be used for reactivity calculation in sodium cooled fast reactors.
- Sodium cooled fast reactor,
- Power reactivity feedback,
- Control rod drive mechanism expansion

FullText(HTML)

References(7)

References

[1]	苏著亭, 叶长源, 阎凤文, 等. 钠冷快增殖堆[M]. 北京: 中国原子能出版社, 1991: 575.
[2]	李泽华. 反应性功率系数测量导则: CEFR01HWLTDT03[R]. 北京: 中国原子能科学研究院, 2005.
[3]	李泽华. 应用三维节块法程序计算动态参数[J]. 核科学与工程,1997, 17(3): 276-280.
[4]	李泽华. 中国实验快堆首炉堆芯的稳态物理特性: CEFR01Z19LWS10-JS[R]. 北京: 中国原子能科学研究院, 2001.
[5]	VANIER M, BERGEONNEAU P, GAUTHIER J C, et al. Superphénix reactivity and feedback coefficients[J]. Nuclear Science and Engineering, 1990, 106(1): 30-36. doi: 10.13182/NSE90-A23754
[6]	IAEA. Comparative assessment of thermophysical and thermohydraulic characteristics of lead, lead-bismuth and sodium coolants for fast reactors: IAEA-TECDOC-1289[R]. Vienna: IAEA, 2002.
[7]	田和春. 求解反应堆动态方程的插值多项式法[J]. 核动力工程,1989, 10(6): 39-46.