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Oral presentation

Study on fabrication and property of nitride fuel for MA transmutation

Takaki, Seiya; Takano, Masahide

no journal, , 

Nitride fuel with ZrN or TiN matrix have been studied for transmutation of minor actinide (MA). These are supposed to be designed as solid solution or compounds with MA nitride from 20 mol% to 40 mol%. From the above, composition and temperature dependence of thermal conductivity for safety evaluation of the fuel have been studied with a little of MA. In the present study, we are aimed to clarify composition and temperature dependence of thermal conductivity and electric conductivity of Dy$$_{x}$$Zr$$_{1-x}$$N solid solution as MA surrogate nitride fuel in order to understand the thermal conduction mechanism of MA nitride fuel physically. In addition to, we introduce studies about pyrochemical compatibility between Dy$$_{x}$$Zr$$_{1-x}$$N (x=0, 0.3) and candidate material for cladding, and entrusted to Japan Atomic Energy Agency by the Ministry of Education, Culture, Sports, Science and Technology of Japan (MEXT).

Oral presentation

Oral presentation

Investigation for transmutation system on double-strata fuel cycle

Oizumi, Akito; Sugawara, Takanori; Iwamoto, Hiroki; Nishihara, Kenji; Tsujimoto, Kazufumi

no journal, , 

no abstracts in English

Oral presentation

Study of radiolysis of HONTA extractant for MA/Ln separation

Toigawa, Tomohiro; Suzuki, Hideya; Ban, Yasutoshi; Ishii, Sho; Matsumura, Tatsuro

no journal, , 

Degradation of extractants and generation of radiolytic products are considered as problem for feasibility of the minor actinides separation process. In this study, degradation amount of hexaoctyl-nitrilotriacetamide (HONTA), which is a candidate extaractant for MA/Ln separation, and its products yields were obtained by using $$gamma$$-rays emitted from Co-60. Our results showed the cleavage sites in HONTA radiolysis and suggest that the mechanism for HONTA radiolysis is differ depending on the absorbed dose.

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