Dose Assessment Method for Control Room Habitability in Accident Condition in Nuclear Power Plants

YANG Dong; TANG Shaohua; WANG Jianhua

Volume 33 Issue 2

Mar. 2025

Turn off MathJax

Article Contents

Abstract

References

Article Navigation > Nuclear Power Engineering > 2012 > 33(2): 123-126

YANG Dong, TANG Shaohua, WANG Jianhua. Dose Assessment Method for Control Room Habitability in Accident Condition in Nuclear Power Plants[J]. Nuclear Power Engineering, 2012, 33(2): 123-126.

Citation:

YANG Dong, TANG Shaohua, WANG Jianhua. Dose Assessment Method for Control Room Habitability in Accident Condition in Nuclear Power Plants[J]. Nuclear Power Engineering, 2012, 33(2): 123-126.

YANG Dong, TANG Shaohua, WANG Jianhua. Dose Assessment Method for Control Room Habitability in Accident Condition in Nuclear Power Plants[J]. Nuclear Power Engineering, 2012, 33(2): 123-126.

Citation:

YANG Dong, TANG Shaohua, WANG Jianhua. Dose Assessment Method for Control Room Habitability in Accident Condition in Nuclear Power Plants[J]. Nuclear Power Engineering, 2012, 33(2): 123-126.

PDF( 297 KB)

Dose Assessment Method for Control Room Habitability in Accident Condition in Nuclear Power Plants

China Nuclear Power Engineering Company Ltd., Shenzhen, Guangdong. 518124, China

Received Date: 2010-10-11
Rev Recd Date: 2011-07-20

Available Online: 2025-03-08

Abstract

Abstract

Based on the NRC technical requirements on NPP control room habitability assessment,and considering the characteristics of the improved second generation NPPs in China,this paper developed a complete dose assessment model for control room habitability.Contrasting to the existing model in China,this model is applicable for DBA and severity accident,and the short term atmospheric diffusion factor can be calculated using the combined wake mode.By considering the zoning of habitable area and the design characteristics of the ventilation system,the effects of un-filtrated air leakage from the building and the ventilation system on the assessment calculation can be considered.
- Control room,
- Habitability,
- Finite plum,
- Effective dose

FullText(HTML)

References(0)

References

Relative Articles

[1]	Zhu Tenghao, Wang Hongtao, Wang Haitao. Research on Vibration-induced Noise Simulation of Main Control Room of High-temperature Gas-cooled Reactor[J]. Nuclear Power Engineering, 2024, 45(6): 132-138. doi: 10.13832/j.jnpe.2024.06.0132
[2]	Xu Funan, Wang Guangjun, Wu Ying. Research on Airtightness Test of Habitable Zone in Main Control Room of HPR1000[J]. Nuclear Power Engineering, 2024, 45(2): 231-234. doi: 10.13832/j.jnpe.2024.02.0231
[3]	Zhu Wei, Hou Qinmai, Cai Ning, Xu Sai, Zhu Jie, Li Qiuqi. Analysis on Validity of Test Data of Primary Circuit Pressure Boundary Leakage Rate[J]. Nuclear Power Engineering, 2022, 43(6): 174-179. doi: 10.13832/j.jnpe.2022.06.0174
[4]	Wang Chao, Shi Yanming, Zhang Yanle. Study on the Habitable Dose Model of Internal Leakage in Main Control Room of Nuclear Power Plant[J]. Nuclear Power Engineering, 2022, 43(4): 143-146. doi: 10.13832/j.jnpe.2022.04.0143
[5]	Cheng Xi, Zhou Guozheng, Tang Ximing, Liang Jun, Zhao Bowen. Effectiveness Assessment and Statistics of Eddy Current Signal in Measuring Oxide Layer of Fuel Rods[J]. Nuclear Power Engineering, 2020, 41(1): 49-53. doi: 10.13832/j.jnpe.2020.01.0049
[6]	Shen Dongming, Cai Jiantao, He Rui, Huang Xiaoming. Data Reliability Analysis during Containment Leakage Test Based on Statistical Software R[J]. Nuclear Power Engineering, 2020, 41(5): 99-103.
[7]	Wang Qi, Wang Kai, Wang Jianhua. Effects of Internal Leakage Pathwayon Main Control Room Habitable Dose in Accident Condition of Nuclear Power Plants[J]. Nuclear Power Engineering, 2020, 41(5): 162-167.
[8]	Zhang Qi, Cao Guanghui, Geng Yan, Kong Jing, Liu Peng, Chen Zixi. Analysis of Effectiveness of Medium Voltage Mobile Power Supplies in M310 and Modified Nuclear Power Plants[J]. Nuclear Power Engineering, 2019, 40(4): 81-84.
[9]	Chen Qingqing, Zhang Li, Hu Hong, Qing Tao, Dai Licao. Study on Human Reliability of Operator in Digital Main Control Room[J]. Nuclear Power Engineering, 2019, 40(4): 104-107.
[10]	Li Hui, Li Chaofeng, Shi Yanming, Xiong Min. Study on Impact of Leakage of Toxic and Hazardous Gases on Habitability of Main Control Room Based on ALOHA[J]. Nuclear Power Engineering, 2019, 40(1): 126-130. doi: 10.13832/j.jnpe.2019.01.0126
[11]	Wang Wanhong, Zhu Dahuan, Peng Changhong, Guo Yun. Uncertainty Analysis for Parameters of CFAST Based on Electrical Cabinet Fire Scenario in Main Control Room[J]. Nuclear Power Engineering, 2018, 39(2): 153-156. doi: 10.13832/j.jnpe.2018.02.0153
[12]	Jiang Xialan, Liu Taili, Liu Yi, Zhang Xuan. Effectiveness Analysis for Core Coolant Monitoring System during Medium Loss of Coolant Accident[J]. Nuclear Power Engineering, 2017, 38(3): 115-118. doi: 10.13832/j.jnpe.2017.03.0115
[13]	Yang Yang. Research of MCR Inleakage Tracer Gas Test of AP1000 Nuclear Power Plant[J]. Nuclear Power Engineering, 2017, 38(1): 131-134. doi: 10.13832/j.jnpe.2017.01.0131
[14]	GUAN Zhonghua, XIANG Qingan, CHEN Bin, YU Hongxing. Probability Analysis for Effectiveness of IVR Strategy during Severe Accidents for ACP1000 through ROAAM[J]. Nuclear Power Engineering, 2015, 36(6): 56-60. doi: 10.13832/j.jnpe.2015.06.0056
[15]	Shi Shaobo, Shen Ping, Tian Xianglu, Gao Luyang. Validity Analysis of Rolled Plugs of Steam Generators Tube[J]. Nuclear Power Engineering, 2015, 36(5): 72-74. doi: 10.13832/j.jnpe.2015.05.0072
[16]	Jin Yue, Bao Han, Liu Xiaojing, Cheng Xu. Assessment of In-Vessel Retention for Advanced Large Size PWRs[J]. Nuclear Power Engineering, 2015, 36(3): 135-141. doi: 10.13832/j.jnpe.2015.03.0135
[17]	Li Bing, CheN Yingying, Xiao Jun, Yang Duanjie, Cui Hao. Discussion on Control Room Habitability Assessment[J]. Nuclear Power Engineering, 2014, 35(4): 65-69. doi: 10.13832/j.jnpe.2014.04.0065
[18]	ZOU Jie, TONG Lili, CAO Xuewu, GU Jian, XUE Junfeng, JIANG Yu, HAO Lulu, CHOU Suchen, LIU Li. Analysis of Hydrogen Source Term and Effectiveness of Hydrogen Control in Thousand Megawatt PWR Severe Accident[J]. Nuclear Power Engineering, 2013, 34(S1): 47-50.
[19]	CAO Ke-mei, XU Yi-quan, SHI Guo-bao, CAI Jian-ping. ERVC Effectiveness Analysis for Three-Layer Configuration Molten Pool[J]. Nuclear Power Engineering, 2013, 34(4): 20-22,94.
[20]	CHEN Xing, ZHANG Shishun, LIN Jiming. Assessment of In-Vessel Corium Retention in CPR1000[J]. Nuclear Power Engineering, 2011, 32(3): 6-9,24.