2MW液态钍基熔盐实验堆主屏蔽温度场分析  

Temperature field analysis for the main shielding of the 2-MW thorium-based molten salt experimental reactor

作　　者：何杰[1,2] 夏晓彬[1] 蔡军[1] 潘登[1,2] 彭玉[1,2] 黄建平[1] 张国庆[1] 

机构地区：[1]中国科学院上海应用物理研究所,嘉定园区,上海201800 [2]中国科学院大学,北京100049

出　　处：《核技术》2016年第4期57-63,共7页Nuclear Techniques

基　　金：中国科学院战略性先导科技专项项目(No.XDA02050200)资助~~

摘　　要：反应堆主屏蔽是核反应堆的重要组成部分,用来有效降低反应堆运行时屏蔽体外的辐射剂量水平,以满足反应堆部件材料对辐射限制的要求。温度是影响反应堆主屏蔽性能的重要因素。针对2 MWth液态熔盐堆(2-MW liquid-fueled molten salt experimental reactor,TMSR-LF1),采用MCNP软件获得功率分布后,利用Fluent软件对主屏蔽进行温度场计算。计算过程中利用Python语言编写了程序(MCNP to Fluent,MTF)来实现将MCNP(Monte Carlo N Particle Transport Code)计算结果转换为功率密度的空间分布,以用户自定义函数(User-Defined Function,UDF)形式导入到Fluent,解决了MCNP计算结果不能直接导入到Fluent的问题,并分别计算了TMSR-LF1熔盐堆不同环境温度下的主屏蔽温度场分布情况。结果表明,在环境温度为5°C、18°C、25°C、30°C、35°C、40°C情况下,TMSR-LF1熔盐堆主屏蔽普通混凝土墙温度均低于要求限值,达到设计要求。Background： Molten salt reactor is a fourth generation advanced reactor. The concrete wall is the key part of this high-temperature reactor shielding, so temperature field analysis is important. Purpose： This study attempts to calculate the temperature field of the TMSR-LF1 （2-MW liquid-fueled molten salt experimental reactor） shielding, and judge if it meets the design requirements. Methods： In accordance with the problem that MCNP （Monte Carlo N Particle Transport Code） results cannot be directly imported into Fluent, a program which converts MCNP results to the spatial distribution of power density, and imports the spatial distribution of power density into the Fluent in the form of User-Defined Function （UDF） was developed by using Python programming language to realize the coupling of the two. According to TMSR-LF 1 design parameters, a one-eight physical and thermal model of the whole reactor is established, using code MCNP and Fluent. Reactor radiation shielding thermal analysis adopts the assumptions that the different environment temperatures are 5℃, 18℃, 25℃, 30℃, 35℃ and 40℃, respectively. Results： The maximal values of temperature and temperature gradient in the radiation shielding concrete wall are 67.42℃ and 78.40℃·m^-1, which are lower than limit values. Conclusion： The radiation shielding concrete wall can meet the design requirements.

关 键 词：MCNP Fluent数值模拟 熔盐堆 

分 类 号：TL364[核科学技术—核技术及应用]