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Transition to thorium fuel cycle in a small modular molten salt reactor based on a batch reprocessing mode

机译:基于分批后处理模式的小型模块化熔融盐反应器向to燃料循环的过渡

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摘要

There is currently a renewed interest in small modular reactor (SMR) and molten salt reactor (MSR) concepts, since the former is recognized as the most accessible form of nuclear energy with a lower cost compared to conventional reactors while the latter is considered as one of the reference reactors of the Generation IV International Forum (GIF) suited for thorium fuel cycle. The TRUs from the spent fuel of LWRs containing more than 50% of fissile fuels may be used to start up a MSR due to its outstanding features of no fuel assembly and online/batch reprocessing. This study aims to analyze the characteristics of a small modular thorium-based molten salt reactor (sm-TMSR) using TRUs and Th as fissile and fertile fuels towards thorium fuel cycle with a batch reprocessing mode. The neutronic properties using TRUs as an igniting fuel in the core configurations with the fuel salt fraction (SF) of 18.4%/27.4% and the reprocessing periods (RPs) of 5/10 years are first analyzed and compared. To obtain a high production of U233, the configuration with SF = 27.4% and RP = 5 years is recommended. The recovered uranium production and the purity of U233 can achieve similar to 69 kg/y and over 75%, respectively. Furthermore, the recovered uranium demand with thorium fuel cycle in the 27.4% core and other thermal sm-TMSRs are evaluated. In the 27.4% core, the recovered uranium demand during 40-year operation is similar to 38 kg/y. For the new sm-TMSRs with the SF ranging from 2% to 18.4%, the recovered uranium demand varies from 148 to 48 kg/y. Finally, transition scenarios to thorium fuel cycle are proposed. The transition time is about 22 years in the 27.4% core while it is about 28 years in the SF = 18.4% core. The simulated results demonstrate that it is feasible to achieve the transition from TRUs to thorium fuel cycle in sm-TMSRs if a batch reprocessing mode can be adopted. (C) 2019 Elsevier Ltd. All rights reserved.
机译:当前,人们对小型模块化反应堆(SMR)和熔融盐反应堆(MSR)的概念重新产生了兴趣,因为与常规反应堆相比,前者被认为是最容易获得的核能形式,且成本较低。第四代国际论坛(GIF)的参考反应堆适用于for燃料循环。由于轻水堆乏燃料中含有50%以上的易裂变燃料,其TRU由于无需燃料组装和在线/批处理的突出特点,可用于启动MSR。这项研究旨在分析使用TRUs和Th作为可裂变和肥沃燃料向towards燃料循环,采用分批后处理模式的小型模块化modular基熔融盐反应堆(sm-TMSR)的特性。首先分析并比较了以TRUs为点火燃料的核心结构,其燃料盐分数(SF)为18.4%/ 27.4%,后处理周期(RPs)为5/10年。为了获得高产量的U233,建议使用SF = 27.4%和RP = 5年的配置。回收的铀产量和U233的纯度分别可达到约69千克/年和超过75%。此外,还评估了27.4%堆芯中含with燃料循环的回收铀需求以及其他热电SM-TMSR。在27.4%的核心地区,40年运营期间回收的铀需求约为38千克/年。对于SF范围为2%至18.4%的新型sm-TMSR,回收铀需求量为148至48 kg / y。最后,提出了向or燃料循环的过渡方案。 27.4%核心的过渡时间约为22年,而SF = 18.4%核心的过渡时间约为28年。仿真结果表明,如果可以采用批处理模式,则在sm-TMSR中实现从TRU到to燃料循环的过渡是可行的。 (C)2019 Elsevier Ltd.保留所有权利。

著录项

  • 来源
    《Annals of nuclear energy》 |2020年第4期|107163.1-107163.8|共8页
  • 作者

  • 作者单位

    Chinese Acad Sci Shanghai Inst Appl Phys Shanghai 201800 Peoples R China|Chinese Acad Sci CAS Innovat Acad TMSR Energy Syst Shanghai 201800 Peoples R China|Univ Chinese Acad Sci Beijing 100049 Peoples R China;

    Chinese Acad Sci Shanghai Inst Appl Phys Shanghai 201800 Peoples R China|Chinese Acad Sci CAS Innovat Acad TMSR Energy Syst Shanghai 201800 Peoples R China;

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  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    Small modular molten salt reactors; Thorium fuel cycle; TRUs; U233 production; Transition scenario;

    机译:小型模块化熔盐反应堆;ium燃料循环;TRU;U233生产;过渡方案;

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