Enhancement of oxidation tolerance of graphite materials for high temperature gas-cooled reactor

Mizuta, Naoki; Sumita, Junya; Shibata, Taiju; Osaki, Takashi*; Kato, Hideki*; Izawa, Shoichi*; Muto, Takenori*; Gizatulin, S.*; Sakaba, Nariaki

Tanso Zairyo Kagaku No Shinten; Nihon Gakutsu Shinkokai Dai-117-Iinkai 70-Shunen Kinen-Shi, p.161 - 166, 2018/10

To enhance oxidation resistance of graphite material for in-core components of HTGR, JAEA and four Japanese graphite companies; Toyo Tanso, IBIDEN, Tokai Carbon and Nippon Techno-Carbon, are carrying out for development of oxidation-resistant graphite by CVD-SiC coating. This paper describes the outline of neutron irradiation test about the oxidation-resistant graphite by WWR-K reactor of INP, Kazakhstan through an ISTC partner project. Prior to the irradiation test, the oxidation-resistant graphite by CVD-SiC coating of all specimens showed enough oxidation resistance under un-irradiation condition. The neutron irradiation test was already completed and out-of-pile oxidation test will be carried out at the hot-laboratory of WWR-K.

Surface and interface structural studies by SR-X-rays

Mizuki, Junichiro

Zairyo Kagaku, 35(3), p.155 - 163, 1998/05

no abstracts in English

Prospects of alloy design for zircaloy cladding

;

Zairyo Kagaku, 16(4,5), p.173 - 179, 1979/00

no abstracts in English

Molten solt LiF-BeF(flibe) system and its applications; molten slag,molten-salt breeden reactor,fusion reactor,etc

Furukawa, Kazuo;

Zairyo Kagaku, 14(6), p.302 - 309, 1977/06

no abstracts in English

Radiation Damage in Metals

Zairyo Kagaku, 9(3), p.135 - 140, 1972/06

no abstracts in English

Nucliar Fusion Reactors and Materials

;

Zairyo Kagaku, 9(2), p.85 - 89, 1972/04

no abstracts in English