Best Estimate Plus Uncertainty Method and Its Application

RAN Xu; WU Dan; CHEN Bing-de; ZHANG Yu

Volume 34 Issue 3

Mar. 2025

Turn off MathJax

Article Contents

Abstract

References

Article Navigation > Nuclear Power Engineering > 2013 > 34(3): 120-123

RAN Xu, WU Dan, CHEN Bing-de, ZHANG Yu. Best Estimate Plus Uncertainty Method and Its Application[J]. Nuclear Power Engineering, 2013, 34(3): 120-123.

Citation:

RAN Xu, WU Dan, CHEN Bing-de, ZHANG Yu. Best Estimate Plus Uncertainty Method and Its Application[J]. Nuclear Power Engineering, 2013, 34(3): 120-123.

RAN Xu, WU Dan, CHEN Bing-de, ZHANG Yu. Best Estimate Plus Uncertainty Method and Its Application[J]. Nuclear Power Engineering, 2013, 34(3): 120-123.

Citation:

RAN Xu, WU Dan, CHEN Bing-de, ZHANG Yu. Best Estimate Plus Uncertainty Method and Its Application[J]. Nuclear Power Engineering, 2013, 34(3): 120-123.

PDF( 241 KB)

Best Estimate Plus Uncertainty Method and Its Application

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

Received Date: 2011-12-30
Rev Recd Date: 2012-02-10

Available Online: 2025-03-08

Abstract

Abstract

Best estimate plus uncertainty method could be used to eliminate the over-conservatism in the current method and gain more safety margin.In the current paper,uncertainty method which has considered the effect of the initial conditions,boundary conditions,and model uncertainties has been developed based on the best estimate code RELAP5.This method was used to analyze the NEPTUN reflood experiment.The results showed that the new method was reasonable.
- Best estimate,
- Uncertainty,
- NEPTUN,
- Reflood,

FullText(HTML)

References(0)

References

Relative Articles

[1]	Wang Xiaohu, Zhao Pinghui, Ye Taohong, Xiong Yan, Tan Chao, Chen Yunlong. Research on Correction Method of Pressure Spike at Gas-Liquid Interface Crossing Cells Based on RELAP5[J]. Nuclear Power Engineering, 2024, 45(1): 34-40. doi: 10.13832/j.jnpe.2024.01.0034
[2]	Xu Rongshuan, Xia Hang, Xu Caihong, He Dongyu, Wang Ting, Li Jinggang. Verification and Uncertainty Evaluation of LOCUST Reflood Model[J]. Nuclear Power Engineering, 2024, 45(4): 111-117. doi: 10.13832/j.jnpe.2024.04.0111
[3]	Zhao Wei, Chen Lixin, Liu Guodong, Zhang Liang, Yang Ning, Zhang Xinyi, Tian Xiaoyan, Sun Peiwei, Yuan Jianxin. Multi-scale Coupling Transient Characteristics of Xi 'an Pulsed Reactor Based on RELAP5 and CTF[J]. Nuclear Power Engineering, 2023, 44(3): 59-64. doi: 10.13832/j.jnpe.2023.03.0059
[4]	Li Xiang, Sun Wan, Ding Shuhua, Huang Tao, Li Zhongchun, Pan Liangming. Study on CCFL Characteristics in Downcomer during Discharge Phase of LOCA with RELAP5 Code[J]. Nuclear Power Engineering, 2022, 43(3): 58-65. doi: 10.13832/j.jnpe.2022.03.0058
[5]	Zeng Wei, Wang Jie, Huang Tao, Chen Wei, Ding Shuhua, Deng Chengcheng, Yang Jun. Study on Important Phenomenon Identification and Numerical Simulation Uncertainty Analysis for PWR Large Break LOCA[J]. Nuclear Power Engineering, 2021, 42(1): 198-203. doi: 10.13832/j.jnpe.2021.01.0198
[6]	Zhao Ningning, Yuan Hongsheng, Wen Qinglong, Ruan Shenhui. Evaluation of the Impact of Core Power Distribution on Reflooding Phenomenon in CCTF Test[J]. Nuclear Power Engineering, 2021, 42(6): 58-64. doi: 10.13832/j.jnpe.2021.06.0058
[7]	Liu Yusheng, Xu Chao, Hu Jian, Zhuang Shaoxin, Fang Fangfang. Numerical Analysis of ACME Station Blackout Integral Effect Test with Relap[J]. Nuclear Power Engineering, 2019, 40(3): 98-102. doi: 10.13832/j.jnpe.2019.03.0097
[8]	Xian Lin, Jiang Guangming, Li Jie, Wang Xiaoji, Yang Fan, Li Feng, Ran Xu. Improvement and Validation of Free Convection Heat Transfer Model for Tube Bundle in RELAP5[J]. Nuclear Power Engineering, 2018, 39(3): 29-32. doi: 10.13832/j.jnpe.2018.03.0029
[9]	Liang Weihong, Xie Heng. Analyses on Flow Instability of Secondary-Side Passive Residual Heat Removal System for Advanced Nuclear Heating Reactor[J]. Nuclear Power Engineering, 2018, 39(2): 14-19. doi: 10.13832/j.jnpe.2018.02.0014
[10]	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
[11]	Wang Chenglong, Hu Lingwen, Qiu Suizheng, Su Guanghui, Tian Wenxi. Uncertainty Analysis of Transportable Fluoride-Salt-Cooled High Temperature Reactor（TFHR）[J]. Nuclear Power Engineering, 2017, 38(3): 168-171. doi: 10.13832/j.jnpe.2017.03.0168
[12]	Gong Houjun, Xi Zhao, Zan Yuanfeng, Zhuo Wenbin, Huang Yanping. Sensitivity Study on Secondary Side Passive Residual Heat Removal System Based on RELAP5[J]. Nuclear Power Engineering, 2016, 37(6): 11-14. doi: 10.13832/j.jnpe.2016.06.0011
[13]	Hao Chen, Zhao Qiang, Li Fu, Yu Yan, Zhang Chunyan, Zhang Huiyan. Uncertainty Analysis of Advanced Pressurized Water Reactor Fuel Assembly[J]. Nuclear Power Engineering, 2016, 37(3): 173-180. doi: 10.13832/j.jnpe.2016.03.0173
[14]	Fang Jun, Wu Nan, Qi Ting. Applicability Research of RELAP5 for Steam Generator Tube Rupture Accident of AP1000 NPP[J]. Nuclear Power Engineering, 2016, 37(3): 70-74. doi: 10.13832/j.jnpe.2016.03.0070
[15]	Shi Chengbin, Cheng Maosong, Liu Guimin. Extending and Verification of RELAP5 Code for Liquid Fueled Molten Salt Reactor[J]. Nuclear Power Engineering, 2016, 37(3): 16-20. doi: 10.13832/j.jnpe.2016.03.0016
[16]	Xiong Wanyu, Gong Houjun, Xi Zhao, Zhuo Wenbin, Huang Yanping. Preliminary Evaluation of RELAP5 for Design of Secondary Side Passive Residual Heat Removal System[J]. Nuclear Power Engineering, 2015, 36(2): 143-146. doi: 10.13832/j.jnpe.2015.02.0143
[17]	LÜ Li, Yu Tao, Yu Hongxing, Wu Dan, Xie Jinsen, Peng Huanhuan. Research on Wall-to-Vapor Convective Heat Transfer Model in Reflooding Phase of Typical PWR Based on RELAP5[J]. Nuclear Power Engineering, 2015, 36(2): 42-45. doi: 10.13832/j.jnpe.2015.02.0042
[18]	Li Dong, Xu Wei, Liu Xiaojing, Yang Yanhua. Improvement of RELAP5 Models Related to Reflood Phenomenon Based on Sensitivity Analysis[J]. Nuclear Power Engineering, 2015, 36(S2): 151-156. doi: 10.13832/j.jnpe.2015.S2.0151
[19]	ZENG Wei, ZHU Li, LIU Song-tao, YU Hong-xing, SUN Yu-fa. Research on Effect of Two-Phase Interfacial Friction Characteristics on Quench Front Velocity in Narrow Channel[J]. Nuclear Power Engineering, 2013, 34(6): 66-69,74.
[20]	ZENG Wei, YU Hong-xing, SUN Yu-fa, LI Feng. Research on Reflood Model of Narrow Channel Based on RELAP5[J]. Nuclear Power Engineering, 2013, 34(3): 50-57.