ThorCon堆氚产额分析研究
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摘要
ThorCon堆是一种以熔融氟盐(Na F-Be F2-Th F4-UF4)作为燃料及冷却剂、石墨为慢化剂的小型模块化熔盐反应堆。在热中子的照射下熔盐中的Be、F以及屏蔽层和石墨中的B会发生核反应产生氚。氚在高温下具有很强的渗透能力,能够影响金属构件的力学性能,减少其使用寿命。进入环境的氚在高温下易氧化为氚化水。氚化水进入人体后会形成内照射,对操作人员健康造成影响。根据产氚反应的性质及中间产物个数可将产氚反应分为三类:直接产氚反应、有中间产物的产氚反应、三裂变产氚反应。并对这三类反应分别建立相应的计算方程。计算结果表明,ThorCon堆年产氚约为5.444 g。其中Be反应产氚是最主要的氚来源,88.5%的氚来源于Be。如能降低Be含量,将大幅降低氚的产额。
[Background] ThorCon reactor is a thermal reactor using molten salt(Na F-Be F2-Th F4-UF4) as fuel and coolant and graphite as moderator. Tritium would be produced by nuclear reaction of Be, F in Na F-Be F2-Th F4-UF4 and B graphite, which has strong penetration ability at high temperature, affecting the mechanical properties of the structure and reduce its life. And the tritium is easily changed into trialed water, which may enter the human body, causing internal radiation. [Purpose] This paper aims to predict the production of tritium and its main reaction. [Methods] The tritium production reaction was divided into three types based on the number of intermediate products in the reaction channel, such as producing tritium by nuclear reactions with or without intermediate products and by ternary fission. Three corresponding equations were set up accordingly. [Results] The results showed that the annual tritium production was about 5.444 g, and 88.5% of tritium came from Be. [Conclusion] If the amount of Be can be reduced, the yield of tritium will be greatly reduced.
[Background] ThorCon reactor is a thermal reactor using molten salt(Na F-Be F2-Th F4-UF4) as fuel and coolant and graphite as moderator. Tritium would be produced by nuclear reaction of Be, F in Na F-Be F2-Th F4-UF4 and B graphite, which has strong penetration ability at high temperature, affecting the mechanical properties of the structure and reduce its life. And the tritium is easily changed into trialed water, which may enter the human body, causing internal radiation. [Purpose] This paper aims to predict the production of tritium and its main reaction. [Methods] The tritium production reaction was divided into three types based on the number of intermediate products in the reaction channel, such as producing tritium by nuclear reactions with or without intermediate products and by ternary fission. Three corresponding equations were set up accordingly. [Results] The results showed that the annual tritium production was about 5.444 g, and 88.5% of tritium came from Be. [Conclusion] If the amount of Be can be reduced, the yield of tritium will be greatly reduced.
引文
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3李厚文.秦山核电厂氚的年生成量[J].核动力工程,2001,(3):285-288.DOI:10.3969/j.issn.0258-0926.2001.03.020.LI Houwen.Annual product of 3H in Qinshan nuclear power plant[J].Nuclear Power Engineering,2001,(3):285-288.DOI:10.3969/j.issn.0258-0926.2001.03.020.
4宫权,周静,刘昱.AP1000正常运行工况气液态放射性流出物释放量研究[J].核科学与工程,2014,34(4):547-553.GONG Quan,ZHOU Jing,LIU Yu.Study on radioactive release of gaseous and liquid effluents during normal operation of AP1000[J].Nuclear Science and Engineering,2014,34(4):547-553.
5杨雪.AP1000型核电机组运行期间的预期氚排放[J].辐射防护通讯,2012,32(1):8-12.DOI:10.3969/j.issn.1004-6356.2012.01.002.YANG Xue.The research of AP1000 expected tritium release during normal operation[J].Radiation Protection Bulletin,2012,32(1):8-12.DOI:10.3969/j.issn.1004-6356.2012.01.002.
6 GB 6249-2011:核动力厂环境辐射防护规定[S].2011.GB 6249-2011:Regulations for environmental radiation protection of nuclear powerplant[S].2011.
7彭超,朱兴望,张国庆,等.采用SCALE计算氟盐冷却高温堆产氚量的一些问题[J].核技术,2015,38(8):080601.DOI:10.11889/j.0253-3219.2015.hjs.38.080601.PENG Chao,ZHU Xingwang,ZHANG Guoqing,et al.Issues in the calculation of the tritium production of the fluoride-salt-cooled high-temperature reactors using SCALE[J].Nuclear Techniques,2015,38(8):080601.DOI:10.11889/j.0253-3219.2015.hjs.38.080601.
8徐博.小型模块化固态燃料熔盐堆TMSR-SF2的热工水力设计与安全事故分析[D].上海:中国科学院上海应用物理研究所,2017.XU Bo.The thermal hydraulic design and accident analyses of small module solid fuel fluoride salt reactor TMSR-SF2[D].Shanghai:Shanghai Institute of Applied Physics,Chinese Academy of Sciences,2017.
9陈海英,张春明,王韶伟,等.压水堆3H源项计算分析[J].原子能科学技术,2016,50(3):459-463.DOI:10.7538/yzk.2016.50.03.0459.CHEN Haiying,ZHANG Chunming,WANG Shaowei,et al.Calculation analysis of tritium source term in PWR[J].Atomic Energy Science and Technology,2016,50(3):459-463.DOI:10.7538/yzk.2016.50.03.0459.
10张晶,李厚文.秦山三期重水堆核电站流出物氚排放的比较分析[J].辐射防护,2009,29(2):80-85.ZHANG Jing,LI Houwen.Analysis of effluence tritium release from Qinshan phase III heavy water reactor[J].Radiation Protection,2009,29(2):80-85.