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Journal Articles

Irradiation test plan of oxidation-resistant graphite in WWR-K research reactor

Sumita, Junya; Shibata, Taiju; Sakaba, Nariaki; Osaki, Hiroki*; Kato, Hideki*; Fujitsuka, Kunihiro*; Muto, Takenori*; Gizatulin, S.*; Shaimerdenov, A.*; Dyussambayev, D.*; et al.

Proceedings of 7th International Topical Meeting on High Temperature Reactor Technology (HTR 2014) (USB Flash Drive), 7 Pages, 2014/10

Graphite materials are used for the in-core components of High Temperature Gas-cooled Reactor(HTGR)which is a graphite-moderated and helium gas-cooled reactor. In the case of air ingress accident in HTGR, SiO$$_{2}$$ protective layer is formed on the surface of SiC layer in TRISO CFP and oxidation of SiC does not proceed and fission products are retained inside the fuel particle. A new safety concept for the HTGR, called Naturally Safe HTGR, has been recently proposed. To enhance the safety of Naturally Safe HTGR ultimately, it is expected that oxidation-resistant graphite is used for graphite components to prevent the TRISO CFPs and fuel compacts from failure. SiC coating is one of candidate methods for oxidation-resistant graphite. JAEA and four graphite companies launched R&Ds to develop the oxidation-resistant graphite and the International Science and Technology Center(ISTC) partner project with JAEA and INP was launched to investigate the irradiation effects on the oxidation-resistant graphite. To determine grades of the oxidation-resistant graphite which will be adopted as irradiation test, a preliminary oxidation test was carried out. This paper described the results of the preliminary oxidation test, the plan of out-of-pile test, irradiation test and post-irradiation test(PIE)of the oxidation-resistant graphite.

Oral presentation

Collaboration with Republic of Kazakhstan regarding development of HTGR, 3; Collaboration of development of oxidation-resistant graphite material for HTGR

Shibata, Taiju; Sumita, Junya; Nagata, Hiroshi; Saito, Takashi; Tsuchiya, Kunihiko; Sakaba, Nariaki; Osaki, Hiroki*; Kato, Hideki*; Fujitsuka, Kunihiro*; Muto, Takenori*; et al.

no journal, , 

no abstracts in English

Oral presentation

Oxidation test of oxidation-resistant graphite manufactured by Tokai Carbon

Fujitsuka, Kunihiro*; Kondo, Akira*; Sumita, Junya; Sakaba, Nariaki; Fukuda, Toshiaki*

no journal, , 

High Temperature Gas-cooled Reactor (HTGR) including High Temperature engineering Test Reactor (HTTR) constructed by Japan Atomic Energy Agency (JAEA) and Very High Temperature Reactor (VHTR) are able to supply high temperature helium gas at the reactor outlet, and possess inherent safety. Fine-Grained isotropic graphite with high strength is used for the in-components of HTGR. In the case of severe accident, for example air ingress accident, it is desirable that oxidation-resistant graphite is used for the in-component of HTGR. One of the effective methods for oxidation-resistant property on graphite is to coat the surface with ceramics, such as SiC, which forms SiO$$_{2}$$ layer when it oxidizes. This method is one of the general industrial methods called chemical vapor deposition (CVD). Tokai Carbon Co., Ltd. (Tokai carbon) and JAEA launched R&Ds to develop the oxidation-resistant graphite. Tokai Carbon manufactured the oxidation-resistant graphite coated with SiC by CVD etc., and oxidation test and observation of surface condition before and after oxidation were carried out. Moreover, irradiation test using WWR-K research reactor in Institute of Nuclear Physics of the Republic of Kazakhstan (INP) was carried out and post-irradiation examination will begin soon. This presentation shows the oxidation behaviour of the oxidation-resistant graphite according to weight change of specimens, and the surface condition of the specimen according to surface and cross section observation of specimens before and after oxidation.

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