氯盐快堆具有重金属溶解度高和能谱较硬等特性,是嬗变超铀核素(Transuranic elements,TRU)的理想堆型。本文提出了一种50 MW小型模块化氯盐快堆(small-Modular Chlorine salt Fast Reactor,sm-MCFR)方案,对其焚烧TRU特性进行了初步研究...氯盐快堆具有重金属溶解度高和能谱较硬等特性,是嬗变超铀核素(Transuranic elements,TRU)的理想堆型。本文提出了一种50 MW小型模块化氯盐快堆(small-Modular Chlorine salt Fast Reactor,sm-MCFR)方案,对其焚烧TRU特性进行了初步研究。采用了基于SCALE(Standardized Computer Analyses for Licensing Evaluation)和MODEC(MOlten Salt Reactor Specific DEpletion Code)开发的耦合程序TMCBurnup(TRITON MODEC Coupled Burnup Code),计算并分析了sm-MCFR在TRU+232Th和TRU+DU(Depleted Uranium)两种燃料方案下的临界、燃耗、核素演化和嬗变TRU等物理性能。结果表明:在sm-MCFR运行期间,为维持临界状态,需在线添加TRU,以确保有效增殖系数k_(eff)>1;满功率运行40 a时,采用TRU+Th燃料方案下堆芯剩余TRU量为657 kg,而采用TRU+DU燃料方案下剩余TRU量为725 kg,皆大于寿期初;采用TRU+Th和TRU+DU作为燃料盐时,嬗变率分别可达49%和41%,为实现乏燃料最小化提供了可行方案。展开更多
Due to their unique features,such as the inherent safety,simplified fuel cycle,and continuous on-line reprocessing,molten salt reactors(MSRs)are regarded as one of the six reference reactors in the Generation IV Inter...Due to their unique features,such as the inherent safety,simplified fuel cycle,and continuous on-line reprocessing,molten salt reactors(MSRs)are regarded as one of the six reference reactors in the Generation IV International Forum(GEN-IV).Molten chloride salt fast reactors(MCFRs)are a type of MSR.Compared to molten fluoride salt reactors(MFSRs),MCFRs have a higher solubility of heavy metal atoms,a harder neutron spectrum,lower accumulation of fission products(FPs),and better breeding and transmutation performance.Thus,MCFRs have been recognized as a type of MSR with great prospects for future development.However,as the most important feature for MSRs,the effect of different reprocessing modes on MCFRs must be researched in depth.As such,this study investigated the effect of different isotopes,especially FPs,on the neutronic performance of an MCFR,such as its breeding performance.Furthermore,the characteristics of the different reprocessing modes and MCFR rates were analyzed in terms of safety,radioactivity level,neutron economy,and breeding capacity.In the end,a reprocessing method suitable for MCFRs was determined through calculation and analysis,which provides a reference for the further research of MCFRs.展开更多
与氟盐堆相比,氯盐快堆具有超铀核素(Transuranics,TRU)溶解度更高、中子能谱更硬、熔点更低等方面的优势。基于熔盐嬗变堆(Molten Salt Actinide Recycler and Transmuter,MOSART)的堆芯结构,采用熔盐堆在线添料和后处理程序MSR-RS(Mol...与氟盐堆相比,氯盐快堆具有超铀核素(Transuranics,TRU)溶解度更高、中子能谱更硬、熔点更低等方面的优势。基于熔盐嬗变堆(Molten Salt Actinide Recycler and Transmuter,MOSART)的堆芯结构,采用熔盐堆在线添料和后处理程序MSR-RS(Molten Salt Reactor Reprocessing Sequence)进行分析,针对氯盐快堆的熔盐组成、后处理方式等方面进行了优化,以利于提升其增殖及嬗变性能。首先分析了不同载体盐和启动燃料对燃耗性能的影响,提出了熔盐成分优化方案;然后引入离线批处理和在线连续处理两种后方式来提升燃耗性能。结果表明:在氯盐快堆中,高重金属溶解度的Na Cl更适合作为载体盐;TRU中的次锕系核素(Minor Actinides,MA)有助于提升增殖性能;采用离线批处理能够达到较好的燃耗性能,降低对后处理系统的要求。优化后的堆芯燃耗时间延长到31 a,相应的燃耗深度提高至210 GW·d·t^(-1)左右,233U的积累量达到8 300 kg,并且最终消耗了约12 000 kg的TRU,嬗变率为62.1%。展开更多
基于熔盐嬗变堆(Molten Salt Actinide Recycler and Transmuter,简称MOSART)堆芯结构对氯盐快堆(Molten Chloride Salt Fast Reactor,简称MCFR)进行了优化,分析了熔盐成分和后处理方式的影响,使其燃耗性能得到明显的提升,但是相比熔盐...基于熔盐嬗变堆(Molten Salt Actinide Recycler and Transmuter,简称MOSART)堆芯结构对氯盐快堆(Molten Chloride Salt Fast Reactor,简称MCFR)进行了优化,分析了熔盐成分和后处理方式的影响,使其燃耗性能得到明显的提升,但是相比熔盐快堆(Molten Salt Fast Reactor,简称MSFR)的增殖及嬗变性能仍有一定差距。基于在线连续添料与后处理方式,采用SCALE6.1程序和熔盐堆在线添料和后处理程序(Molten Salt Reactor Reprocessing Sequence,简称MSR-RS)分析了堆芯结构、^(37)Cl富集度对增殖比(Breeding Ratio,简称BR)、核素吸收率、燃耗等方面的影响,提出了双区氯盐快堆的设计,进一步提升了增殖嬗变性能和钍基燃料的利用率,倍增时间缩短到20年左右,超铀核素(Transuranics,简称TRU)嬗变率达到68%左右。展开更多
文摘氯盐快堆具有重金属溶解度高和能谱较硬等特性,是嬗变超铀核素(Transuranic elements,TRU)的理想堆型。本文提出了一种50 MW小型模块化氯盐快堆(small-Modular Chlorine salt Fast Reactor,sm-MCFR)方案,对其焚烧TRU特性进行了初步研究。采用了基于SCALE(Standardized Computer Analyses for Licensing Evaluation)和MODEC(MOlten Salt Reactor Specific DEpletion Code)开发的耦合程序TMCBurnup(TRITON MODEC Coupled Burnup Code),计算并分析了sm-MCFR在TRU+232Th和TRU+DU(Depleted Uranium)两种燃料方案下的临界、燃耗、核素演化和嬗变TRU等物理性能。结果表明:在sm-MCFR运行期间,为维持临界状态,需在线添加TRU,以确保有效增殖系数k_(eff)>1;满功率运行40 a时,采用TRU+Th燃料方案下堆芯剩余TRU量为657 kg,而采用TRU+DU燃料方案下剩余TRU量为725 kg,皆大于寿期初;采用TRU+Th和TRU+DU作为燃料盐时,嬗变率分别可达49%和41%,为实现乏燃料最小化提供了可行方案。
基金supported by the Chinese TMSR Strategic Pioneer Science and Technology Project (No.XDA02010000)the Frontier Science Key Program of Chinese Academy of Sciences (No.QYZDY-SSW-JSC016)the Shanghai Sailing Program (No.20YF1457600).
文摘Due to their unique features,such as the inherent safety,simplified fuel cycle,and continuous on-line reprocessing,molten salt reactors(MSRs)are regarded as one of the six reference reactors in the Generation IV International Forum(GEN-IV).Molten chloride salt fast reactors(MCFRs)are a type of MSR.Compared to molten fluoride salt reactors(MFSRs),MCFRs have a higher solubility of heavy metal atoms,a harder neutron spectrum,lower accumulation of fission products(FPs),and better breeding and transmutation performance.Thus,MCFRs have been recognized as a type of MSR with great prospects for future development.However,as the most important feature for MSRs,the effect of different reprocessing modes on MCFRs must be researched in depth.As such,this study investigated the effect of different isotopes,especially FPs,on the neutronic performance of an MCFR,such as its breeding performance.Furthermore,the characteristics of the different reprocessing modes and MCFR rates were analyzed in terms of safety,radioactivity level,neutron economy,and breeding capacity.In the end,a reprocessing method suitable for MCFRs was determined through calculation and analysis,which provides a reference for the further research of MCFRs.
文摘基于熔盐嬗变堆(Molten Salt Actinide Recycler and Transmuter,简称MOSART)堆芯结构对氯盐快堆(Molten Chloride Salt Fast Reactor,简称MCFR)进行了优化,分析了熔盐成分和后处理方式的影响,使其燃耗性能得到明显的提升,但是相比熔盐快堆(Molten Salt Fast Reactor,简称MSFR)的增殖及嬗变性能仍有一定差距。基于在线连续添料与后处理方式,采用SCALE6.1程序和熔盐堆在线添料和后处理程序(Molten Salt Reactor Reprocessing Sequence,简称MSR-RS)分析了堆芯结构、^(37)Cl富集度对增殖比(Breeding Ratio,简称BR)、核素吸收率、燃耗等方面的影响,提出了双区氯盐快堆的设计,进一步提升了增殖嬗变性能和钍基燃料的利用率,倍增时间缩短到20年左右,超铀核素(Transuranics,简称TRU)嬗变率达到68%左右。
