
浏览全部资源
扫码关注微信
中国科学院上海应用物理研究所 嘉定园区 上海 201800
[ "钱楠, 男, 1985年出生, 2015年于上海交通大学获博士学位, 研究领域为核能科学与工程", "QIAN Nan, male, born in 1985, graduated from Shanghai Jiao Tong University with a doctoral degree in 2015, focusing on nuclear science and engineering" ]
吴胜伟, E-mail:wushengwei@sinap.ac.cnWU Shengwei, E-mail: wushengwei@sinap.ac.cn
刘卫, E-mail:liuwei@sinap.ac.cnLIU Wei, E-mail: liuwei@sinap.ac.cn
收稿日期:2017-09-29,
修回日期:2017-11-27,
纸质出版日期:2018-02-10
移动端阅览
钱楠, 王广华, 黄豫, 等. ThorCon堆氚产额分析研究[J]. 核技术, 2018,41(2):020606
Nan QIAN, Guanghua WANG, Yu HUANG, et al. Issues in the calculation of the tritium production in the ThorCon reactors[J]. Nuclear techniques, 2018, 41(2): 020606
钱楠, 王广华, 黄豫, 等. ThorCon堆氚产额分析研究[J]. 核技术, 2018,41(2):020606 DOI: 10.11889/j.0253-3219.2018.hjs.41.020606.
Nan QIAN, Guanghua WANG, Yu HUANG, et al. Issues in the calculation of the tritium production in the ThorCon reactors[J]. Nuclear techniques, 2018, 41(2): 020606 DOI: 10.11889/j.0253-3219.2018.hjs.41.020606.
ThorCon堆是一种以熔融氟盐(NaF-BeF
2
-ThF
4
-UF
4
)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
2
ThorCon reactor is a thermal reactor using molten salt (NaF-BeF
2
-ThF
4
-UF
4
) as fuel and coolant and graphite as moderator. Tritium would be produced by nuclear reaction of Be
F in NaF-BeF
2
-ThF
4
-UF
4
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
2
This paper aims to predict the production of tritium and its main reaction.
Methods
2
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
2
The results showed that the annual tritium production was about 5.444 g
and 88.5% of tritium came from Be.
Conclusion
2
If the amount of Be can be reduced
the yield of tritium will be greatly reduced.
孙 国民 , 程 懋松 , 戴 志敏 . 小型模块化熔盐快堆燃料管理初步分析 . 核技术 , 2016 . 39 ( 7 ): 070603 DOI: 10.11889/j.0253-3219.2016.hjs.39.070603 http://doi.org/10.11889/j.0253-3219.2016.hjs.39.070603 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract623.shtml .
Guomin SUN , Maosong CHENG , Zhimin DAI . Preliminary analysis of fuel management for a small modular molten salt fast reactor . Nuclear Techniques , 2016 . 39 ( 7 ): 070603 DOI: 10.11889/j.0253-3219.2016.hjs.39.070603.hjs.39.070603 http://doi.org/10.11889/j.0253-3219.2016.hjs.39.070603.hjs.39.070603 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract623.shtml .
刘 群 . 小型核反应堆在美国的商业前景及启示 . 中国核工业 , 2016 . ( 8 ): 30 - 32 . http://www.doc88.com/p-5909581667208.html .
Qun LIU . Prospects and enlightenment of small nuclear reactor in the United States . China Nuclear Industry , 2016 . ( 8 ): 30 - 32 . http://www.doc88.com/p-5909581667208.html .
李 厚文 . 秦山核电厂氚的年生成量 . 核动力工程 , 2001 . ( 3 ): 285 - 288 . DOI: 10.3969/j.issn.0258-0926.2001.03.020 http://doi.org/10.3969/j.issn.0258-0926.2001.03.020 .
Houwen LI . Annual product of 3 H in Qinshan nuclear power plant . Nuclear Power Engineering , 2001 . ( 3 ): 285 - 288 . DOI: 10.3969/j.issn.0258-0926.2001.03.020 http://doi.org/10.3969/j.issn.0258-0926.2001.03.020 .
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 . 核科学与工程 , 2014 . 34 ( 4 ): 547 - 553 . http://www.cnki.com.cn/Article/CJFDTOTAL-FSFH201504001.htm .
Quan GONG , Jing ZHOU , Yu LIU . Study on radioactive release of gaseous and liquid effluents during normal operation of AP1000 . Nuclear Science and Engineering , 2014 . 34 ( 4 ): 547 - 553 . http://www.cnki.com.cn/Article/CJFDTOTAL-FSFH201504001.htm .
杨 雪 . AP1000型核电机组运行期间的预期氚排放 . 辐射防护通讯 , 2012 . 32 ( 1 ): 8 - 12 . DOI: 10.3969/j.issn.1004-6356.2012.01.002 http://doi.org/10.3969/j.issn.1004-6356.2012.01.002 .
Xue YANG . The research of AP1000 expected tritium release during normal operation . Radiation Protection Bulletin , 2012 . 32 ( 1 ): 8 - 12 . DOI: 10.3969/j.issn.1004-6356.2012.01.002 http://doi.org/10.3969/j.issn.1004-6356.2012.01.002 .
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.
彭 超 , 朱 兴望 , 张 国庆 , . 采用SCALE计算氟盐冷却高温堆产氚量的一些问题 . 核技术 , 2015 . 38 ( 8 ): 080601 DOI: 10.11889/j.0253-3219.2015.hjs.38.080601 http://doi.org/10.11889/j.0253-3219.2015.hjs.38.080601 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract456.shtml .
Chao PENG , Xingwang ZHU , Guoqing ZHANG , . Issues in the calculation of the tritium production of the fluoride-salt-cooled high-temperature reactors using SCALE . Nuclear Techniques , 2015 . 38 ( 8 ): 080601 DOI: 10.11889/j.0253-3219.2015.hjs.38.080601 http://doi.org/10.11889/j.0253-3219.2015.hjs.38.080601 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract456.shtml .
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. http: //cdmd. cnki. com. cn/Article/CDMD-80014-1017811016. htm
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.
陈 海英 , 张 春明 , 王 韶伟 , . 压水堆 3 H源项计算分析 . 原子能科学技术 , 2016 . 50 ( 3 ): 459 - 463 . DOI: 10.7538/yzk.2016.50.03.0459 http://doi.org/10.7538/yzk.2016.50.03.0459 .
Haiying CHEN , Chunming ZHANG , Shaowei WANG , . Calculation analysis of tritium source term in PWR . Atomic Energy Science and Technology , 2016 . 50 ( 3 ): 459 - 463 . DOI: 10.7538/yzk.2016.50.03.0459 http://doi.org/10.7538/yzk.2016.50.03.0459 .
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 . 辐射防护 , 2009 . 29 ( 2 ): 80 - 85 . http://www.cqvip.com/QK/91042X/200902/29906338.html .
Jing ZHANG , Houwen LI . Analysis of effluence tritium release from Qinshan phase Ⅲ heavy water reactor . Radiation Protection , 2009 . 29 ( 2 ): 80 - 85 . http://www.cqvip.com/QK/91042X/200902/29906338.html .
0
浏览量
22
下载量
0
CSCD
关联资源
相关文章
相关作者
相关机构
京公网安备11010802024621