熔盐实验堆堆芯结构变化对反应性的影响分析
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摘要
熔盐堆采用液态燃料,由于燃料的流动性,堆芯结构的变化会直接影响堆芯活性区的燃料盐装载量,从而影响堆芯物理特性参数。本文基于蒙特卡罗程序MCNP(Monte Carlo N Particle Transport Code),以2 MW液态燃料钍基熔盐堆(Thorium Molten Salt Reactor-Liquid Fuel,TMSR-LF1)设计模型为参考,系统研究了套管破裂、石墨构件移动、石墨破损、燃料盐浸渗度等因素对堆芯反应性的影响。结果表明:对于堆芯套管破裂,堆芯引入正反应性,破裂位置离堆芯中心越近,引入的反应性越大;对于石墨构件移动,随着扇形石墨构件向外移动,堆芯反应性增加;对于堆芯石墨破损,破损发生后,原燃料盐流道被石墨堵住时,则堆芯反应性减小;对于堆芯石墨破损,破损发生后,新燃料盐流道形成时,当石墨破损半径较小时,堆芯反应性会增加,当石墨破损半径较大时,堆芯反应性会减小。对于堆芯石墨发生燃料盐浸渗,堆芯反应性增加,且燃料盐渗入量越大,反应性变化越大。本研究为2 MW TMSR-LF1安全分析提供参考依据。
[Background] Liquid fuel is used in the molten salt reactor, altering core structure will cause direct change of fuel salt loading and affect the physical parameters of the reactor core duel to flowing fuel. [Purpose] This study aims at the influence of core structure changes on reactivity. [Methods] The 2 MW thorium molten salt reactorliquid fuel(TMSR-LF1) model was taken as the reference reactor, and the reactivity varitions were calculated by using MCNP(Monte Carlo N particle transport code) with consideration of parameter changes caused by channel tube rupture, graphite component movement, graphite damage, and fuel salt penetration. [Results] Computational results reveal that casing rupture leads to positive reactivity in reactor core, the closer the rupture location is to the core center, the greater the reactivity is introduced. When the graphite component moves outward, the reactivity of the reactor core increases. When core graphite is damaged, decrease of the reactivity appears in the case of the original fuel salt channel blocked by graphite. In the case of new fuel salt channel formed through the damaged graphite the reactivity will increase when the graphite damage radius is small, and decrease when the graphite damage radius is large. The permeability of fuel salts in the core increases reactivity, and the greater the permeability of fuel salts, the greater the impact on reactivity. [Conclusions] This study provides a basic reference for safety analysis of 2 MW TMSR-LF1.
[Background] Liquid fuel is used in the molten salt reactor, altering core structure will cause direct change of fuel salt loading and affect the physical parameters of the reactor core duel to flowing fuel. [Purpose] This study aims at the influence of core structure changes on reactivity. [Methods] The 2 MW thorium molten salt reactorliquid fuel(TMSR-LF1) model was taken as the reference reactor, and the reactivity varitions were calculated by using MCNP(Monte Carlo N particle transport code) with consideration of parameter changes caused by channel tube rupture, graphite component movement, graphite damage, and fuel salt penetration. [Results] Computational results reveal that casing rupture leads to positive reactivity in reactor core, the closer the rupture location is to the core center, the greater the reactivity is introduced. When the graphite component moves outward, the reactivity of the reactor core increases. When core graphite is damaged, decrease of the reactivity appears in the case of the original fuel salt channel blocked by graphite. In the case of new fuel salt channel formed through the damaged graphite the reactivity will increase when the graphite damage radius is small, and decrease when the graphite damage radius is large. The permeability of fuel salts in the core increases reactivity, and the greater the permeability of fuel salts, the greater the impact on reactivity. [Conclusions] This study provides a basic reference for safety analysis of 2 MW TMSR-LF1.
引文
1 Bettis E S,Schroeder R W,Cristy G A,et al.The aircraft reactor experiment-design and construction[J].Nuclear Science and Engineering,1957,2:804-825.
2 Haubenreich R C.MSRE design and operations report part?Description of reactor[R].ORNL-TM-728.Tennessee,America:ORNL,1965.
3 Haubenreich P N,Engel J R,Prince B E,et al.MSREdesign and operations report partⅢnuclear analisis[R].ORNL-TM-730.Tennessee,America:ORNL,1964.
4刘亚芬,梅龙伟,蔡翔舟.熔盐堆不同堆芯边界下的物理研究[J].核技术,2013,36(3):030601.DOI:10.11889/j.0253-3219.2013.hjs.36.030601.LIU Yafen,MEI Longwei,CAI Xiangzhou.Physics research for Molten Salt Reactor with different core boundaries[J].Nuclear Techniques,2013,36(3):030601.DOI:10.11889/j.0253-3219.2013.hjs.36.030601.
5叶奇蓁,李晓明,俞忠德,等.中国电气工程大典第6卷:核能发电工程[M].北京:中国电力出版社,2009:1142-1144.YE Qizhen,LI Xiaoming,YU Zhongde,et al.China electrical engineering canon sixth volume nuclear power generation engineering[M].Beijing:China Electric Power Press,2009:1142-1144.
6 Merle-Lucotte E,Heuer D,Allibert M,et al.Introduction to the physics of Molten Salt Reactors[R].NATOAdvanced Study Institute on Materials Issues for Generation IV Systems:Status,Open Questions and Challenges,Corsica,France,2007.
7蔡翔舟,戴志敏,徐洪杰.钍基熔盐堆核能系统[J].物理,2016,45(9):578-590.CAI Xiangzhou,DAI Zhimin,XU Hongjie.Thorium molten salt reactor nuclear energy system[J].Physics,2016,45(9):578-590.
8 Pelowitz D B.MCNP6TM user's manual[R].Los Alamos,NM,USA:Los Alamos National Laboratory,LA-CP-13-00634,2013.
9张宝亮,戚威,夏汇浩,等.核石墨的孔结构与熔盐浸渗特性研究[J].核技术,2017,40(12):120605.DOI:10.11889/j.0253-3219.2017.hjs.40.120605.ZHANG Baoliang,QI Wei,XIA Huihao,et al.Porosity properties and molten salt impregnation characteristics of nuclear graphites[J].Nuclear Techniques,2017,40(12):120605.DOI:10.11889/j.0253-3219.2017.hjs.40.120605.
2 Haubenreich R C.MSRE design and operations report part?Description of reactor[R].ORNL-TM-728.Tennessee,America:ORNL,1965.
3 Haubenreich P N,Engel J R,Prince B E,et al.MSREdesign and operations report partⅢnuclear analisis[R].ORNL-TM-730.Tennessee,America:ORNL,1964.
4刘亚芬,梅龙伟,蔡翔舟.熔盐堆不同堆芯边界下的物理研究[J].核技术,2013,36(3):030601.DOI:10.11889/j.0253-3219.2013.hjs.36.030601.LIU Yafen,MEI Longwei,CAI Xiangzhou.Physics research for Molten Salt Reactor with different core boundaries[J].Nuclear Techniques,2013,36(3):030601.DOI:10.11889/j.0253-3219.2013.hjs.36.030601.
5叶奇蓁,李晓明,俞忠德,等.中国电气工程大典第6卷:核能发电工程[M].北京:中国电力出版社,2009:1142-1144.YE Qizhen,LI Xiaoming,YU Zhongde,et al.China electrical engineering canon sixth volume nuclear power generation engineering[M].Beijing:China Electric Power Press,2009:1142-1144.
6 Merle-Lucotte E,Heuer D,Allibert M,et al.Introduction to the physics of Molten Salt Reactors[R].NATOAdvanced Study Institute on Materials Issues for Generation IV Systems:Status,Open Questions and Challenges,Corsica,France,2007.
7蔡翔舟,戴志敏,徐洪杰.钍基熔盐堆核能系统[J].物理,2016,45(9):578-590.CAI Xiangzhou,DAI Zhimin,XU Hongjie.Thorium molten salt reactor nuclear energy system[J].Physics,2016,45(9):578-590.
8 Pelowitz D B.MCNP6TM user's manual[R].Los Alamos,NM,USA:Los Alamos National Laboratory,LA-CP-13-00634,2013.
9张宝亮,戚威,夏汇浩,等.核石墨的孔结构与熔盐浸渗特性研究[J].核技术,2017,40(12):120605.DOI:10.11889/j.0253-3219.2017.hjs.40.120605.ZHANG Baoliang,QI Wei,XIA Huihao,et al.Porosity properties and molten salt impregnation characteristics of nuclear graphites[J].Nuclear Techniques,2017,40(12):120605.DOI:10.11889/j.0253-3219.2017.hjs.40.120605.