Art

J-GLOBAL ID：201502209134557377   Reference number：15A1226204

Chlorination of UO₂ and (U,Zr)O₂ solid solution using MoCl₅

MoCl₅を用いるUO₂及び(U,Zr)O₂固溶体の塩素化

Author (5)： SATO Takumi (Japan Atomic Energy Agency, Ibaraki, JPN) ,  SHIBATA Hiroki (Japan Atomic Energy Agency, Ibaraki, JPN) ,  HAYASHI Hirokazu (Japan Atomic Energy Agency, Ibaraki, JPN) ,  TAKANO Masahide (Japan Atomic Energy Agency, Ibaraki, JPN) ,  KURATA Masaki (Japan Atomic Energy Agency, Ibaraki, JPN)
Material： Journal of Nuclear Science and Technology  (J Nucl Sci Technol)
Volume： 52  Issue： 9-10  Page： 1253-1258  Publication year： Sep. 2015 
JST Material Number： W2314A  ISSN： 0022-3131  Document type： Article
Article type： 原著論文  Country of issue： United Kingdom (GBR)  Language： ENGLISH (EN)

Thesaurus term： *chlorination(chemical reaction) ,  PWR type reactor ,  *molybdenum chloride ,  *nuclear fuel reprocessing ,  *reactor accident ,  *solid solution ,  uranium oxide ,  zirconium oxide ,  *pretreatment ,  temperature gradient ,  uranium chloride ,  zirconium chloride
Semi thesaurus term： Three Mile Island-2 reactor ,  *pyrochemical process ,  *燃料デブリ ,  *Fukushima Nuclear Accident

JST classification (1)： Reprocessing  (MD08050C)

Reference (20)：

• Olsen CS, Jensen SM, Carlson ER, et al. Materials interactions and temperatures in the Three Mile Island unit 2 Core. Nucl Technol. 1988;87:57-94.
• Hofmann P, Hagen S, Schanz G, et al. Reactor core materials interactions at very high temperatures. Nucl Technol. 1988;87:146-186.
• Fuel Debris Conditioning Technology Development Group, Fukushima Project Team, Nuclear Fuel Cycle Engineering Laboratories Fuel Debris Analysis Technology Development Group, and Fukushima Project Team. Nuclear Science Research Institute Fuel debris characterization and treatment technologies development for TEPCO's Fukushima Daiichi Nuclear Power Station: 2012 annual research and development report. Japan: Japan Atomic Energy Agency; 2014. (Report no. JAEA-Review 2013-066).
• Akers DW, Carlson ER, Cook BA, et al. TMI-2 core debris grab samples: examination and analysis part 1. USA: EG and G Idaho, Inc.; 1986.( Report no. GEND-INF-075-PT1).
• Ikeuchi H, Ishihara M, Yano K, et al. Dissolution behavior of (U,Zr)O₂-based simulated fuel debris in nitric acid. J Nucl Sci Technol. 2014;51:996-1005.

Terms in the title (6)： MoCl5 ,  UO2 ,  Zr ,  O2 ,  固溶体 ,  塩素化