锂(Li)元素是液态熔盐堆中冷却剂熔盐的重要组成成分,由于^6Li相对^7Li具有较大的中子吸收截面,其在冷却剂熔盐中的摩尔含量会影响液态熔盐堆的钍铀转换性能,因此研究7Li富集度对液态熔盐堆钍铀转换性能的影响十分必要。基于熔盐快堆(Mo...锂(Li)元素是液态熔盐堆中冷却剂熔盐的重要组成成分,由于^6Li相对^7Li具有较大的中子吸收截面,其在冷却剂熔盐中的摩尔含量会影响液态熔盐堆的钍铀转换性能,因此研究7Li富集度对液态熔盐堆钍铀转换性能的影响十分必要。基于熔盐快堆(Molten Salt Fast Reactor,MSFR)的堆芯结构,分别采用FLi和FLiBe两种不同的冷却剂熔盐,选取范围在99.5%~99.995%的一系列^7Li富集度,借助熔盐堆后处理程序MSR-RS(Molten Salt Reactor Reprocessing Sequence),针对能谱、^233U初装量、钍铀转换比、^233U净产量和倍增时间、Li的演化以及氚产量等一系列参数进行分析。研究结果表明:在MSFR的堆芯中,较FLiBe而言,采用FLi作载体盐能够获得更好的钍铀转换性能;当^7Li富集度由99.995%变为99.9%时,堆芯钍铀转换比降低约1.6%,氚产量增加约8%。综合考虑燃料制造成本和钍铀转换性能等因素,对于分别采用FLi和FLiBe作载体盐的熔盐快堆MSFR,推荐的^7Li富集度都为99.9%。展开更多
The molten salt fast reactor(MSFR) shows great promise with high breeding ratio(BR),large negative temperature coefficient of reactivity,high thermal-electric conversion efficiency,inherent safety,and online reprocess...The molten salt fast reactor(MSFR) shows great promise with high breeding ratio(BR),large negative temperature coefficient of reactivity,high thermal-electric conversion efficiency,inherent safety,and online reprocessing.Based on an improved MSFR optimized by adding axial fertile salt and a graphite reflector,the influences of ~7Li enrichment on Th-U breeding are investigated,aiming to provide a feasible selection for the molten salt with high fissile breeding and a relatively low technology requirement for ~7Li concentration.With the self-developed molten salt reactor reprocessing sequence based on SCALE6.1,the burn-up calculations with online reprocessing are carried out.Parameters are explored including BR,^(233)U production,double time(DT),spectrum,~6Li inventory,neutron absorption,and the tritium production.The results show that the Li enrichment of 99.95% is appropriate in the fast fission reactor.In this case,BR above 1.10 can be achieved for a long time,corresponding to the ^(233)U production of130 kg per year and DT of 36 years.After 80 years' operation,the tritium production for 99.5% is only about 7kg,and there is no obvious increase compared to that for 99.9995%.展开更多
文摘锂(Li)元素是液态熔盐堆中冷却剂熔盐的重要组成成分,由于^6Li相对^7Li具有较大的中子吸收截面,其在冷却剂熔盐中的摩尔含量会影响液态熔盐堆的钍铀转换性能,因此研究7Li富集度对液态熔盐堆钍铀转换性能的影响十分必要。基于熔盐快堆(Molten Salt Fast Reactor,MSFR)的堆芯结构,分别采用FLi和FLiBe两种不同的冷却剂熔盐,选取范围在99.5%~99.995%的一系列^7Li富集度,借助熔盐堆后处理程序MSR-RS(Molten Salt Reactor Reprocessing Sequence),针对能谱、^233U初装量、钍铀转换比、^233U净产量和倍增时间、Li的演化以及氚产量等一系列参数进行分析。研究结果表明:在MSFR的堆芯中,较FLiBe而言,采用FLi作载体盐能够获得更好的钍铀转换性能;当^7Li富集度由99.995%变为99.9%时,堆芯钍铀转换比降低约1.6%,氚产量增加约8%。综合考虑燃料制造成本和钍铀转换性能等因素,对于分别采用FLi和FLiBe作载体盐的熔盐快堆MSFR,推荐的^7Li富集度都为99.9%。
基金supported by the Chinese TMSR Strategic Pioneer Science and Technology Project(No.XDA02010000)the National Natural Science Foundation of China(No.91326201)the Frontier Science Key Program of the Chinese Academy of Sciences(No.QYZDY-SSW-JSC016)
文摘The molten salt fast reactor(MSFR) shows great promise with high breeding ratio(BR),large negative temperature coefficient of reactivity,high thermal-electric conversion efficiency,inherent safety,and online reprocessing.Based on an improved MSFR optimized by adding axial fertile salt and a graphite reflector,the influences of ~7Li enrichment on Th-U breeding are investigated,aiming to provide a feasible selection for the molten salt with high fissile breeding and a relatively low technology requirement for ~7Li concentration.With the self-developed molten salt reactor reprocessing sequence based on SCALE6.1,the burn-up calculations with online reprocessing are carried out.Parameters are explored including BR,^(233)U production,double time(DT),spectrum,~6Li inventory,neutron absorption,and the tritium production.The results show that the Li enrichment of 99.95% is appropriate in the fast fission reactor.In this case,BR above 1.10 can be achieved for a long time,corresponding to the ^(233)U production of130 kg per year and DT of 36 years.After 80 years' operation,the tritium production for 99.5% is only about 7kg,and there is no obvious increase compared to that for 99.9995%.
