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Analysis of Th-U breeding capability for an accelerator-driven subcritical molten salt reactor 被引量:3

Analysis of Th-U breeding capability for an accelerator-driven subcritical molten salt reactor
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摘要 Accelerator-driven systems based on molten salt fuel have several unique advantages and features for advanced nuclear fuel utilization.The aim of this work was to study the Th-U breeding capability in such systems,known as‘‘accelerator-driven subcritical molten salt reactors’’(ADS–MSRs).Breeding capacities including conversion ratio and net^(233)U production for various subcriticalities and different minor actinides(MA)loadings were analyzed for an ADS–MSR.The results show that the subcriticality of the core has a considerable effect on the Th-U breeding.A high subcriticality is favorable to improving the conversion ratio,increasing the net^(233)U production,and reducing the doubling time.Specifically,the doubling time for k_(eff)of 0.99 is larger than 80 years,while the counterpart for k_(eff)of 0.93 is only approximately22 years.Nevertheless,in an ADS–MSR with a high initial MA loading,MA results in a non-negligible^(233)U depletion in the first two decades,while increasing the net^(233)U production compared to reactors without MA loading.During the 50 years of operation,for the subcritical reactor(k_(eff)0:97)with MA fraction increasing from 1 to 14%,the net^(233)U production increases from 3.94 to 8.24 t. Accelerator-driven systems based on molten salt fuel have several unique advantages and features for advanced nuclear fuel utilization.The aim of this work was to study the Th-U breeding capability in such systems,known as"accelerator-driven subcritical molten salt reactors"(ADS–MSRs).Breeding capacities including conversion ratio and net ^233U production for various subcriticalities and different minor actinides(MA)loadings were analyzed for an ADS–MSR.The results show that the subcriticality of the core has a considerable effect on the Th-U breeding.A high subcriticality is favorable to improving the conversion ratio,increasing the net ^233U production,and reducing the doubling time.Specifically,the doubling time for keff of 0.99 is larger than 80 years,while the counterpart for keffof 0.93 is only approximately22 years.Nevertheless,in an ADS–MSR with a high initial MA loading,MA results in a non-negligible-(233)U depletion in the first two decades,while increasing the net ^233U production compared to reactors without MA loading.During the 50 years of operation,for the subcritical reactor(keff =0.97)with MA fraction increasing from 1 to 14%,the net ^233U production increases from 3.94 to 8.24 t.
出处 《Nuclear Science and Techniques》 SCIE CAS CSCD 2018年第8期218-226,共9页 核技术(英文)
基金 supported by the Chinese TMSR Strategic Pioneer Science and Technology Project(No.XDA02010000) the Frontier Science Key Program of the Chinese Academy of Sciences(No.QYZDY-SSW-JSC016)
关键词 加速器驱动 反应堆 熔融 能力 星期 MSR net Subcritical Molten salt fuel Conversionratio Net ^233U production
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