著者

角田 淳弥 植田 祥平 國富 一彦 吉牟田 秀治 沢 和弘

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会和文論文誌 (ISSN:13472879)

巻号頁・発行日

vol.2, no.4, pp.546-554, 2003-12-25 (Released:2010-03-08)

参考文献数

29

被引用文献数

2 2

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A High Temperature Gas-Cooled Reactor (HTGR) is particularly attractive due to capability of producing high temperature helium gas and its inherent safety characteristic. Research and development of high temperature gas turbine plant and high temperature heat utilizing technology are now undergoing. The High Temperature Engineering Test Reactor (HTTR) is a research facility constructed by the Japan Atomic Energy Research Institute (JAERI). All rise-topower tests have been successfully carried out and the performance of the HTTR has been evaluated. Now, preparation for the operation with outlet coolant temperature of 950°C and safety demonstration tests are undergoing.This paper describes reprocessing technology of HTGR fuels. Coated fuel particles, consisted of a microsphere of low enriched UO2 with TRISO particles, are used as the HTGR fuels. In order to reprocess HTGR fuels, a head-end process is needed and JAERI had confirmed jet-grind method as basic technologies of the head-end process. Since Purex method can be used after the head-end process, a reprocessing system for the HTGR fuels could be established. Also the preliminary study on the methodology for disposing graphite blocks in a HTGR was carried out, and its evaluation results were briefly presented.