Study of annual tritium discharge in pressurized water reactor based on historical data

Fu Pengtao; Dai Mingliang; Zhu Zhaowen; Liu Xinhua; Fang Lan; Xu Chunyan

doi:10.11884/HPLPB202234.210399

Volume 34 Issue 2

Jan. 2022

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Fu Pengtao, Dai Mingliang, Zhu Zhaowen, et al. Study of annual tritium discharge in pressurized water reactor based on historical data[J]. High Power Laser and Particle Beams, 2022, 34: 026009. doi: 10.11884/HPLPB202234.210399

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Fu Pengtao, Dai Mingliang, Zhu Zhaowen, et al. Study of annual tritium discharge in pressurized water reactor based on historical data[J]. High Power Laser and Particle Beams, 2022, 34: 026009. doi: 10.11884/HPLPB202234.210399

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Study of annual tritium discharge in pressurized water reactor based on historical data

doi: 10.11884/HPLPB202234.210399

1.
China Nuclear Power Technology Research Institute Co., Ltd., Shenzhen 518000, China
2.
Nuclear and Radiation Safety Center，Ministry of Ecology and Environment，Beijing 100082, China

Received Date: 2021-09-06
Accepted Date: 2022-01-13
Rev Recd Date: 2022-01-12

Available Online: 2022-01-17

Publish Date: 2022-01-11

Abstract

Abstract

Based on tritium production mechanism and the tritium calculation model in China General Nuclear Power Corporation (CGN), the historic tritium discharges in lots of nuclear power plants around the world have been comprehensively gathered and analyzed. It is recognized that the activation of boric acid in the primary loops and activation of Be in secondary neutron source (40% of annual tritium discharge in CGN’s operating pressurized water reactor units) are the predominant origins, and the tritium release from intact fuel rods with zirconium alloy can be neglected. It is found that use of double encapsulated secondary neutron source or cancellation of secondary neutron source is the only way to reduce significantly the tritium discharges in the pressurized water reactors.
- pressurized water reactor,
- tritium,
- secondary neutron source,
- zirconium alloy,
- stainless steel cladding

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References(37)

References

[1]	IAEA. Management of waste containing tritium and carbon-14[R]. Technical Reports Series No. 421, 2004: 28-35.
[2]	Bechtold T E, Dyer N C. Radionuclides in United States commercial nuclear power reactors[R]. WINCO-1191, 1994: 6-25.
[3]	ASN. Groupes de réflexion menés de mai 2008 à avril 2010 sous l'égide de l'ASN et Bilan annuel des rejets de tritium pour les installations nucléaire de base de 2015 à 2019[R]. 2019: 4-241.
[4]	Jacobs D G. Sources of tritium and its behavior upon release to the environment[R]. TID-24635, 1968: 21-22.
[5]	杨茂春. 压水堆核电站氚的辐射风险分析[J]. 辐射防护通讯, 2000, 20(3):1-6. (Yang Maochun. Radiation risk analysis of tritium in PWR nuclear power plants[J]. Radiation Protection Bulletin, 2000, 20(3): 1-6
[6]	Locante J. Tritium in pressurized water reactors[J]. Transactions of the American Nuclear Society, 1971, 14(1): 161-162.
[7]	Phillips J E, Easterly C E. Sources of tritium[R]. ORNL/TM-6402, 1980: 4-8.
[8]	Hussey D, Saunders P, Morey D, et al. Modeling tritium life cycle in nuclear plants[C]//Proceedings of the Waste Management 2006 Symposium. 2006.
[9]	Jones G. Tritium issues in commercial pressurized water reactors[J]. Fusion Science and Technology, 2008, 54(2): 329-332. doi: 10.13182/FST08-A1824
[10]	单陈瑜, 石秀安, 蔡德昌, 等. 大亚湾和岭澳一期核电站氚年排放量计算分析[J]. 核科学与工程, 2013, 33(1):31-37. (Shan Chenyu, Shi Xiuan, Cai Dechang, et al. Analysis and calculation of annual emissions of tritium for Daya Bay and Ling Ao nuclear power plants[J]. Nuclear Science and Engineering, 2013, 33(1): 31-37 doi: 10.3969/j.issn.0258-0918.2013.01.007
[11]	付鹏涛, 蔡德昌, 李志军. 基于CPR1000的压水堆氚排放量研究[C]//第十七届反应堆数值计算与粒子输运学术会议CORPHY暨2018年反应堆物理会议(CORPHY-2018). 2018 Fu Pengtao, Cai Dechang, Li Zhijun. Study of tritium production based on CPR1000 discharge[C]//CORPHY-2018.2018
[12]	彭思涛, 王超, 赵焱, 等. 中广核自主燃耗计算软件PALM研发[C]//第十七届反应堆数值计算与粒子输运学术会议CORPHY暨2018年反应堆物理会议(CORPHY-2018). 2018 Peng Sitao, Wang Chao, Zhao Yan, et al. Development of the CGN burnup code PALM[C]//CORPHY-2018.2018
[13]	刘鹏, 史敦福, 李康, 等. JMCT与子通道程序耦合方法研究及验证[J]. 强激光与粒子束, 2018, 30:016010. (Liu Peng, Shi Dunfu, Li Kang, et al. Research and validation on coupling method of JMCT and subchannel code[J]. High Power Laser and Particle Beams, 2018, 30: 016010 doi: 10.11884/HPLPB201830.170252
[14]	Bouhrizi S. GDA UK EPR–BAT demonstration[R]. UKEPR-0011-001 Issue 06, 2012.
[15]	U. S. NRC. Westinghouse AP1000 design control document rev. 19[R]. ML11171A500, 2011.
[16]	Zamani M, Tafakkorbari S, Rostami H, et al. Release assessment of tritium in liquid effluents of Bushehr nuclear power plant (BNPP) in 2013[C]//Proceedings of LXIV International conference NUCLEUS 2014. 2014: 261-262.
[17]	van der Stricht S, Janssens A. Radioactive effluents from nuclear power stations and nuclear fuel reprocessing sites in the European Union, 1999-2003[R]. Radiation Protection 143, 2005.
[18]	van der Stricht S, Janssens A. Radioactive effluents from nuclear power stations and nuclear fuel reprocessing sites in the European Union, 2004-08[R]. Radiation Protection 164, 2010.
[19]	广东大亚湾核电站岭澳核电站生产运行年鉴(1994-2015)[M]. 北京: 原子能出版社, 1994-2015 GNPS & LNPS operation yearbook (1994-2015)[M]. Beijing: Atomic Energy Press, 1994-2015
[20]	付鹏涛. 压水堆氚源项研究[R]. 中广核研究院有限公司, 2018 Fu Pengtao. Study of PWR tritium production[R]. CNPRI, 2018
[21]	付鹏涛. 压水堆氚排放量计算模型及参数的优化研究[R]. 中广核研究院有限公司, 2017 Fu Pengtao. Study of PWR tritium production calculation model and parameter[R]. CNPRI, 2017
[22]	Chretien V, Le Guen B. Rejets de tritium et impact autour des centrales EDF[C]//Proceedings of Tritium Conference in Paris France. 2009: 23-24.
[23]	欧阳俊杰, 陈跃. 大亚湾核电站1994~2002年放射性流出物监测总结[J]. 辐射防护, 2004, 24(3/4):162-172. (Ouyang Junjie, Chen Yue. Summarization of radioactive effluent monitoring in Daya Bay nuclear power station 1994~2002[J]. Radiation Protection, 2004, 24(3/4): 162-172
[24]	Elleman T S, Austin J H, Verghese K. Tritium diffusion in Zircaloy-2 and stainless steels[J]. Transactions of the American Nuclear Society, 1972, 15(1): 229-230.
[25]	Abraham P M, Chandra D, Mintz J M, et al. Diffusion of gases in solids: rare gas diffusion in solids; tritium diffusion in fission and fusion reactor metals[R]. ORO-3508-10, 1976.
[26]	Gilbert E R, Allen R P, Baldwin D L, et al. Tritium permeation and related studies on barrier treated 316 stainless steel[R]. PNL-SA-19113, 1991.
[27]	Dollè L, Houdaille B, Leger D, et al. Tritium in fission reactors, production and management[J]. The International Journal of Applied Radiation and Isotopes, 1980, 31: 463.
[28]	Yario W R. Tritium inventory and release from core materials[J]. The International Journal of Applied Radiation and Isotopes, 1980, 31: 462.
[29]	Andrieu C, Rave S, Ducros G, et al. Release of fission tritium through Zircaloy-4 fuel cladding tubes[J]. Journal of Nuclear Materials, 2005, 347(1/2): 12-19.
[30]	Westinghouse Electric Company. Secondary sources-double encapsulated secondary source assemblies (SSAs)[R]. NFCM-0013, 2013.
[31]	Meyer G, Stokke E. Description of Sizewell B nuclear power plant[R]. NKS/RAK-2(97)TR-C4, 1997: 1-3.
[32]	Crouail P, Jeannin B, Lefaure C, et al. Organisation of radiation protection at Sizewell nuclear power plant in the UK[R]. Contract N°647/EDF, 2004: 35-47.
[33]	陈忠宇, 张勇. 秦山核电厂大修期间辐射源项分析[J]. 辐射防护, 2009, 29(2):65-71. (Chen Zhongyu, Zhang Yong. Analysis of source terms during refuiling outage at Qinshan nuclear power plant[J]. Radiation Protection, 2009, 29(2): 65-71
[34]	Homyk W A, Peters J, Quan B, et al. Antimony/beryllium neutron source leakage at Indian Point 2[J]. Radiation Protection Management, 1992, 9(3): 65-80.
[35]	The Committee on the Safety of Nuclear Installations of the OECD Nuclear Energy Agency. Leaking secondary neutron source in reactor coolant system[R]. 2002: 29-35.
[36]	章安龙. 反应堆无二次中子源装料和启动[J]. 核科学与工程, 2019, 39(3):345-349. (Zhang Anlong. Reactor reloading and startup without secondary neutron source[J]. Nuclear Science and Engineering, 2019, 39(3): 345-349 doi: 10.3969/j.issn.0258-0918.2019.03.002
[37]	费罗杰, 勒瑞. 取消昌江核电厂二次中子源的理论探究[J]. 设备管理与维修, 2015(s2):13-16. (Fei Luojie, Le Rui. Theoretical research of abandon of secondary neutron source in Changjiang nuclear power plant[J]. Plant Maintenance Engineering, 2015(s2): 13-16