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熔盐反应堆——放射化学创新发展的新源泉 被引量:2

Molten Salt Reactor:A New Source of Innovation Development for Radiochemistry
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摘要 本文从放射化学视角简略介绍了熔盐堆及其在钍铀燃料循环应用中的优势,然后叙述了与熔盐堆相关的放射化学研究的三个方向:即燃料供给、辐照后燃料的再处理以及熔盐堆运行的工艺监测和核素诊断。在燃料的再处理中推荐了一种类似文献报道的AIROX流程的干法后处理的新技术路线,指出其在熔盐堆在线燃料处理中的优点和重要价值。由于熔盐堆的运行中存在大量的化学与放射化学问题,因此熔盐堆堪比"化学堆",放射化学监测和诊断对于熔盐堆的运行有极其重要的意义。由此可见,熔盐堆研发促使形成了放射化学的一门新的分支学科——以监测和诊断为目标的熔盐反应堆化学。最后给出了放射化学工作者在熔盐堆发展过程中应该注意的若干建议。 From the version of radiochemistry, this paper introduced molten salt reactor (MSR) and its advantages in the application of thorium-uranium fuel cycle briefly. Then three radiochemical research fields related to MSR were stated: fuel supply, reprocessing for irradiated fuels, and monitoring and diagnosis during the reactor operation. In the fuel repro- cessing, a novel pyroprocessing technical roadmap, similarly to AIROX flowsheet reported in references, was recommended, and its advantages and important value in on-line fuel processing of MSR were illustrated. Due to great amount of issues on the chemistry and radi- ochemistry occurred in MSR operation, MSR is just like a "chemical reactor", thus radio-chemical monitoring and diagnosis have a significant meaning to the operation of MSR. It is pointed out that a new discipline branch of radiochemistry, i. e. the molten salt reactor chemistry, aiming to the monitoring and diagnosis of MSR is formed. At the end of the paper, some suggestions that radiochemistry researchers should keep in mind during the development progress of MSR were advised.
出处 《核化学与放射化学》 CAS CSCD 北大核心 2016年第6期327-336,共10页 Journal of Nuclear and Radiochemistry
基金 中国科学院战略性科技先导专项--钍基熔盐堆核能系统(XDA02030000) 中国科学院前沿科学重点研究项目--钍铀燃料循环特性和若干关键问题研究(QYZDY-SSW-JSC016)
关键词 熔盐反应堆 放射化学 AIROX 熔盐反应堆化学 molten salt reactor radiochemistry AIROX molten salt reactor chemistry
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  • 1徐光宪.白云鄂博矿钍资源开发利用迫在眉睫[J].稀土信息,2005,11(5):4-5. 被引量:30
  • 2欧阳予.国外核电技术发展趋势(下)[J].中国核工业,2006(3):16-20. 被引量:7
  • 3顾忠茂.解读美国GNEP计划[J].中国核工业,2006(3):27-30. 被引量:2
  • 4贺国珠,易艳玲,孔祥忠.铀-钍混合燃料反应堆的可行性分析[J].原子核物理评论,2006,23(2):101-104. 被引量:3
  • 5顾忠茂.钍资源的核能利用问题探讨[J].核科学与工程,2007,27(2):97-105. 被引量:27
  • 6Uozumi K,Iizuka M,Kato T,et al.Electrocemical Behaviors of U and Pu at Simultaneous Recoveries Into Liquid Cd Cathodes[J].J Nucl Mater,2004,325:34-43.
  • 7Koyama T,Hijikata T,Usami T,et al.Integrated Experiments to Demonstrate Lectrometallurgical Pyroprocessing of Oxide Fuels and Metal Fuels,Oct.9-13,2005[C].Global 2005,CD-ROM,Tsukuba,Ibaraki,Japan,2005.
  • 8Koyama T,Hijikata T,Yokoo T,et al.Development of Engineering Technology Basis for Indisutrialization of Pyroprometallurgical Reprocessing,Sep.9-13,2007[C/CD].Proc Global 2007,Boise,Idaho,2007.
  • 9Shirai O,Kato T,Iwai T,et al.Electrochemical Behaviors of PuN and (U,Pu) N in LiCl-KCl Eutectic Melts[J].J Phys Ceram Solid,2005,66:456.
  • 10Kani Y,Sasahira A,Hoshino K,et al.New Reprocessing System for Spent Nuclear Reactor Fuel Using Fluoride Volatility Method[J].J Fluorine Chem,In Press.

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