期刊文献+

高温气冷堆乏燃料后处理首端技术研究进展 被引量:6

Progress in Head-End Reprocessing of Spent Fuels From High-Temperature Gas-Cooled Reactor
下载PDF
导出
摘要 高温气冷堆乏燃料采用后处理路线能充分利用核资源并减少需要最终地质处置的核废物量,有利于核能的可持续发展。传统的LWR乏燃料后处理首端过程不能用于处理高温气冷堆的乏燃料。高温气冷堆乏燃料元件及包覆层颗粒的破碎是首端处理技术的难点。破碎乏燃料元件及去除石墨的方法主要有机械碾碎法、燃烧法、脉冲电流法等;破碎及去除碳化硅的方法有传统机械碾碎法,以及正在发展中的熔融法、气流喷射粉碎法等,其中,气流喷射粉碎法具有较好的发展前景。目前,尚无一种理想的技术来解决高温气冷堆乏燃料后处理中的首端过程问题,需进一步开展高温气冷堆乏燃料后处理技术的研究。 The reprocessing of high-temperature gas-cooled reactor (HTGR) spent fuels is in favor of the sustainable development of nuclear energy because it is a strategy to realize the maximal use of nuclear resource and the minimum disposal of nuclear waste. The head-end of HTGR spent fuels reprocessing is different from that of the LWR spent fuels reprocessing because of the special structure of HTGR spent fuels. The dismantling of the graphite spent fuel and the smash of the coated granule are the most difficult process in the head-end of the reprocessing. Most of research work is focused on this area. The main methods to treat the graphite include the mechanical grinding, fluid bed burning, and melting, etc. The mechanical grinding method was studied to smash SiC. Some new techniques such as pulse currents method and jet grinding are under investigation. The jet grinding is a promising method. The main pyroreprocessing technology for HTGR spent fuels is the fluoride method. Up to now no ideal technology can solve the problem in the head-end of the reprocessing. It is necessary to speed the further study and develop the new methods.
作者 赵云峰 陈靖
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2008年第5期416-422,共7页 Atomic Energy Science and Technology
关键词 高温气冷堆 乏燃料后处理 首端 high-temperature gas-cooled reactor spent fuel reprocessing head-end
  • 相关文献

参考文献28

  • 1吴宗鑫.我国高温气冷堆的发展[J].核动力工程,2000,21(1):39-43. 被引量:48
  • 2唐春和,肖宏伶.高温气冷堆乏燃料元件的最终处置[J].高技术通讯,2000,10(6):83-86. 被引量:3
  • 3TSUCHIE Y. Desirability of small reactors, HTGR in particular[J].Prog Nucl Energy, 2000, 37(1-4):253-258.
  • 4沈苏,苏宏.高温气冷堆的特点及发展概况[J].东方电气评论,2004,18(1):50-54. 被引量:17
  • 5MOUROGOV V, FUKUDA K, KAGRAMANI- AN V. The need for innovative nuclear reactor and fuel cycle system:Strategy for development and future prospects [J].Prog Nucl Energy, 2002, 40(3-4): 285-299.
  • 6KIRYUSHIN A I, KUZAVKOV N G, RICH- ARDS M, et al. GT-MHR spent fuel storage disposal without processing [R/OL]. Vienna: IAEA, 1997 [ 2007-01-30]. http://www.iaea. org/inis/aws/htgr/abstracts _ c/abst _ 29059914. html.
  • 7DELCUL G D, SPENCER B B, FORSBERG C W, et al. Triso-coated fuel processing to support high-temperature gas-cooled reactors, Tennessee 37831 [R]. Oak Ridge: Oak Ridge National Laboratory, 2002.
  • 8KAISER G, BARNET-WIEMER H, HOOGEN N, et al. Head-end processing of HTR fuel elements [C]//Specialists' Meeting on Gas-Cooled Reactor Fuel Development and Spent Fuel Treatment, Moscow ( Russian Federation), 1983. Moscow: [s. n. ], 1983: 357-368.
  • 9GRENECHE D, MASSON M, BROSSARD P. The reproeessing issue for HTR fuels[C]//An Assessment of Its Interest and Its Feasibility:Global 2003. [S. l.]: [s. n.], 2003: 1 309-1 317.
  • 10BRADLEY M J, FERRIS L M. Recovering uranium from graphite fuel elements[J]. Ind Eng Chem, 1961, S3(4): 279-281.

二级参考文献7

共引文献62

同被引文献65

引证文献6

二级引证文献3

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部