Analysis on Zero Power Experiment of High Flux Engineering Test Reactor with Three-Dimensional Continuous Energy Monte Carlo Code

PENG Gang

Volume 33 Issue 6

Mar. 2025

Turn off MathJax

Article Contents

Abstract

References

Article Navigation > Nuclear Power Engineering > 2012 > 33(6): 127-131,138

PENG Gang. Analysis on Zero Power Experiment of High Flux Engineering Test Reactor with Three-Dimensional Continuous Energy Monte Carlo Code[J]. Nuclear Power Engineering, 2012, 33(6): 127-131,138.

Citation:

PENG Gang. Analysis on Zero Power Experiment of High Flux Engineering Test Reactor with Three-Dimensional Continuous Energy Monte Carlo Code[J]. Nuclear Power Engineering, 2012, 33(6): 127-131,138.

PENG Gang. Analysis on Zero Power Experiment of High Flux Engineering Test Reactor with Three-Dimensional Continuous Energy Monte Carlo Code[J]. Nuclear Power Engineering, 2012, 33(6): 127-131,138.

Citation:

PENG Gang. Analysis on Zero Power Experiment of High Flux Engineering Test Reactor with Three-Dimensional Continuous Energy Monte Carlo Code[J]. Nuclear Power Engineering, 2012, 33(6): 127-131,138.

PDF( 407 KB)

Analysis on Zero Power Experiment of High Flux Engineering Test Reactor with Three-Dimensional Continuous Energy Monte Carlo Code

PENG Gang

Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610041, China

Received Date: 2011-08-26
Rev Recd Date: 2012-04-16

Available Online: 2025-03-08

Abstract

Abstract

Three-dimensional,continuous energy Monte Carlo code（MCNP） is adopted to carry out the analysis of zero power experiment of HFETR.From the results,the impurity,density of Beryllium block and the ¹⁰B concentration in control rod transition part should be carefully determined in the analysis of zero power experiment.While in the experiment of HFETR,the Beryllium block is considered as pure metal and the ¹⁰B concentration in control rod transition part is different from that of zero power experiment.From the calculation results,these parameters（effective neutron multiplication factor k_eff,relative distribution of neutron flux density,γ dose rate distribution and component reactivity） are quite fit with the experiment.The difference of small reactivity between calculation and experiment is quite large,and may be related to the deficiency of MCNP model.
- Three-dimensional core,
- Continuous energy,
- Monte Carlo code（MCNP）,
- High Flux Engineering Test Reactor（HFETR）,
- Zero power experiment

FullText(HTML)

References(0)

References

Relative Articles

[1]	Jiang Duoyu, Xu Peng, Jiang Xinbiao, Hu Tianliang, Wang Lipeng, Cao Lu, Li Da. Application Research on Whole-Core Three-Dimensional Space-Time Kinetics Neutron Transport Code SAAFCGSN[J]. Nuclear Power Engineering, 2025, 46(1): 13-23. doi: 10.13832/j.jnpe.2025.01.0013
[2]	Wang Bo, Zhao Wenbo, Zhang Hongbo, Zhao Chen, Chen Zhang, Liu Kun, Zhang Lerui, Gong Zhaohu, Zeng Wei, Li Qing. Validation of HPR1000 Core Modeling and Startup Test with Three-dimensional Characteristic Neutronics Calculation Code SHARK[J]. Nuclear Power Engineering, 2024, 45(S2): 42-48. doi: 10.13832/j.jnpe.2024.S2.0042
[3]	Xie Aoda, Yang Ting. Research on Nuclear Power System Modeling and Control Methods Based on APROS[J]. Nuclear Power Engineering, 2024, 45(5): 184-191. doi: 10.13832/j.jnpe.2024.05.0184
[4]	Cai Wenchao, Li Songfa, Deng Yunli, Li Changxiang, Feng Haozhi, Qin Fujun, Lu Xing. Determination of Aging Management Scope for HFETR[J]. Nuclear Power Engineering, 2023, 44(S1): 217-222. doi: 10.13832/j.jnpe.2023.S1.0217
[5]	Deng Yunli, Liu Peng, Li Songfa, Wan Qinfang, Dai Yubing, Kang Changhu, Li Jiwa. Time-Limited Aging Analysis for Operating License Extension of HFETR[J]. Nuclear Power Engineering, 2023, 44(S1): 194-198. doi: 10.13832/j.jnpe.2023.S1.0194
[6]	Duan Xinhui, Wang Bingshu, Ji Li. Application of Discontinuity Factor in the Process of ThreeDimensional Reactor Core Transient Simulation[J]. Nuclear Power Engineering, 2018, 39(S2): 173-179. doi: 10.13832/j.jnpe.2018.S2.0173
[7]	Li Ketian, Li Haitao, Liu Peng, Zou Deguang, Cai Wenchao, Zhao Peng, Lai Lisi. Study on Response to Full Open Fault of Degassing Flow Control Valve of HFETR[J]. Nuclear Power Engineering, 2018, 39(S2): 116-120. doi: 10.13832/j.jnpe.2018.S2.0116
[8]	Yang Wenhua, Zhang Liang, Si Junping, Nie Liangbing, Tong Mingyan. Design and Experimental Study of Irradiation Temperature in Fuel Specimen[J]. Nuclear Power Engineering, 2018, 39(6): 43-48. doi: 10.13832/j.jnpe.2018.06.0043
[9]	Li Haitao, Zhou Chunlin, Zou Deguang, Zhang Jiangyun, Wang Wenlong, Xiao Dun, Jiang Tinglan. RELAP5 Model and Test Evaluation of High Flux Engineering Test Reactor[J]. Nuclear Power Engineering, 2018, 39(S2): 112-115. doi: 10.13832/j.jnpe.2018.S2.0112
[10]	Wang Hao, Xiang Yuxin, Xu Taozhong, ZHang Ping, ZHu Lei. Verification of Neutron Flux Calculation Method for HFETR[J]. Nuclear Power Engineering, 2017, 38(S1): 154-156. doi: 10.13832/j.jnpe.2017.S1.0154
[11]	Wu Wenchao, Li Linhong, Li Pu, Chen Qibing, Li Ziyan. Design of Safety Logic Channel Periodic Test Device for HFETR[J]. Nuclear Power Engineering, 2017, 38(5): 77-80. doi: 10.13832/j.jnpe.2017.05.0077
[12]	Liu Hongqian, Liu Shuiqing, Xiang Yuxin, Wang Hao, MA Liyong. Research of Material Irradiation Fine Neutron Flux Spectrum in HFETR[J]. Nuclear Power Engineering, 2017, 38(1): 10-12. doi: 10.13832/j.jnpe.2017.01.0010
[13]	Wang Hao, Liu Shuiqing, Ma Liyong, Yang Bin, Kang Changhu. Calculation and Analysis of Xenon Poison Effect Curve in HFETR[J]. Nuclear Power Engineering, 2016, 37(1): 1-3. doi: 10.13832/j.jnpe.2016.01.0001
[14]	Wang Lianjie, Zhao Wenbo, Yang Ping, Ma Yongqiang, Lu Di, Sun Wei. Development and Verification of Three Dimensional Code System for SCWR Core Steady State Analysis[J]. Nuclear Power Engineering, 2015, 36(4): 41-44. doi: 10.13832/j.jnpe.2015.04.0041
[15]	ZHU Lei, ZHANG Tengfei, SUN Shouhua, XIANG Yuxin, WU Hongchun, ZHENG Youqi, LI Jian. Application of 3-D Core Fuel Management Transport Program for HFETR[J]. Nuclear Power Engineering, 2015, 36(6): 10-13. doi: 10.13832/j.jnpe.2015.06.0010
[16]	Liu Yang, Tong Mingyan, Yang Wenhua, Xu Bin. Development of Modular Tube-Type Irradiation Rig[J]. Nuclear Power Engineering, 2015, 36(S1): 201-203. doi: 10.13832/j.jnpe.2015.S1.0201
[17]	Liu Shuiqing, Sun Yu, MA Liyong, Yang Bin. Estimation of Carbon-14 Production in HFETR[J]. Nuclear Power Engineering, 2014, 35(1): 178-180.
[18]	Hu Yuechun, Li Haitao, DenG Caiyu, Xu Taozhong, MO Zhengyu. Research on Method for Estimating Rapidly Water Temperature of Spent Fuels Storage Pool[J]. Nuclear Power Engineering, 2014, 35(3): 102-104. doi: 10.13832/j.jnpe.2014.03.0102
[19]	Wang Lianjie, Zhao Wenbo, Chen Bingde, Yao Dong, Yang Ping. Development of Coupled 3-D Neutronics/Thermal-Hydraulics Code for SCWR Core Transient Analysis[J]. Nuclear Power Engineering, 2014, 35(S2): 186-189. doi: 10.13832/j.jnpe.2014.S2.0186
[20]	ZhenG Youqi, Wu Hongchun, NeCP team. Development of NECP-SARAX1.0 Code for Fast Reactor Physics Calculation[J]. Nuclear Power Engineering, 2014, 35(S2): 116-118. doi: 10.13832/j.jnpe.2014.S2.0116