原子能科学技术2018，Vol.52Issue(3)：434-440,7.DOI:10.7538/yzk.2017.youxian.0290
氟盐冷却高温堆氚输运特性数值研究
Numerical Analysis of Tritium Transport Characteristics in Fluoride-salt-cooled High-temperature Reactor
摘要
Abstract
Tritium control is one of the most critical issues which limit the development of fluoride salt-cooled high-temperature reactor (FHR).In order to control tritium effectively,the transport characteristics of tritium in fluoride salt must be known.In this paper,the transport characteristics of tritium in the primary loop of FHRs were expounded,including tritium production and speciation,the absorption and desorption by graphite,dissolution and diffusion in molten salt and permeation through structural materials.A series of reasonable mathematical and physical models were established for tritium transport characteristics analysis of TFHR and the TAPAS code for FHRs was developed based on FORTRAN code.The preliminary verification of the code was conducted by comparing calculation results with experiment data,and the results prove the fidelity and accuracy of TAPAS.The tritium transport characteristics in TFHR were analyzed by TAPAS.The initial tritium production rate of TFHR is 5.54 × 10-8 mol/s.Tritium in the primary coolant loop is mainly in the form of T2.The corrosion reactions always occur at the entrance of hot legs.After 25 EFPD operation,tritium absorption by graphite attends its limiting value.When the reactor operates at steady state,the permeation rate of T2 can be regarded as a constant,which is 8.35 μmol/EFPD.This study can contribute to the design and radiation protection of FHR.关键词
氟盐冷却高温堆/氚输运特性/腐蚀/渗透/扩散Key words
FHR/tritium transport characteristics/corrosion/permeation/diffusion分类
能源科技引用本文复制引用
秦浩,王成龙,张大林,田文喜,秋穗正,苏光辉..氟盐冷却高温堆氚输运特性数值研究[J].原子能科学技术,2018,52(3):434-440,7.基金项目
博士后创新人才支持计划资助项目(BX201600124) （BX201600124）
博士后面上基金资助项目(2016M600796) （2016M600796）
高等学校博士学科点专项科研基金(博导类)资助项目(20130201110040) （博导类）
