Investigation of the properties of high temperature resistance alloys used in the helium gas cooled high temperature reactor

Uwaba, Tomoyuki

JNC TN9420 2000-005, 28 Pages, 2000/03

JNC-TN9420-2000-005.pdf:0.94MB

In the first phase of the feasibility study, their basic objectives are presentating the feasible image and scenario of development of the FBR cycle system, which is composed of the fast reactor, spent fuel reprocessing and fuel manufacturing facility. In the development of the FBR system in this phase, various ideas of plants are to be studied, which include coolant types such as sodium, heavy metals, gases(CO, He), wator, and middle or small size of the reactor, and fuel types (MOX, metal and nitride). In this report, as a part of this study, materials used for the core of the helium gas cooled reactor and their integrity (corrosion, mechanical and irradiation property) under high temperature helium atmosphere were investigated from open literatures.

Current status and future R&D for reduced-activation ferritic/martensitic steels

Hishinuma, Akimichi; Koyama, Akira*; R.L.Klueh*; D.S.Gelles*; Ehrlich, K.*; W.Dietz*

Journal of Nuclear Materials, 258-263, p.193 - 204, 1998/00

https://doi.org/10.1016/S0022-3115(98)00395-X

no abstracts in English

Thermal properties of neutron irradiated beryllium

Ishitsuka, Etsuo; Kawamura, Hiroshi; Terai, Takayuki*; Tanaka, Satoru*

Proc. of 5th Int. Workshop on Ceramic Breeder Blanket Interaction, 0, p.215 - 220, 1996/00

no abstracts in English

Development of irradiation properties evaluation technique of accident tolerant fuel cladding tube for advanced nuclear system; Outline of research program

Otsuka, Satoshi; Onuma, Masato*; Mitsuhara, Masatoshi*; Nakashima, Hideharu*; Toyama, Takeshi*; Yano, Yasuhide; Hashidate, Ryuta; Kaito, Takeji

no journal, , 

Fuel cladding tube takes on an important function in fuel safety by confining the fission products in fuel element and keeping the coolant flow path in fuel assembly. Oxide dispersion strengthened (ODS) steels have excellent mechanical strength and dimensional stability. The application of ODS steel for fuel cladding tube of sodium-cooled fast reactor (SFR) can restrain the rupture and excessive deformation of fuel pin, thus enhancing the fuel safety. For implementation of ODS steel cladding tube to the driver fuel of SFR, it is essential to correctly understand its irradiation performance, and improve the reliability of structural integrity under operation. This study carries out the research towards the development of new technique efficiently evaluating irradiation properties of ODS steel on the basis of correlation between mechanical strength and microstructure peculiar to ODS steels, which has been proved by the authors.