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Journal Articles

A Consideration on increasing current density in normal conducting toroidal field coil for spherical tokamak power plant

Song, Y.*; Nishio, Satoshi

Plasma Science and Technology, 7(2), p.2731 - 2733, 2005/04

no abstracts in English

JAEA Reports

The evaluation of material base standard of ODS ferritic stainless steel core component for fast breeder reactors

Mizuta, Shunji; ;

JNC TN9400 2000-048, 28 Pages, 2000/04

JNC-TN9400-2000-048.pdf:0.64MB

ODS (Oxide Dispersion Strengthened) ferritic-martainsitic steels are one of the most prospective cladding materials for advanced fast breeder reactors, since they are expected to have excellent swelling resistance and superior high temperature strength due to the finely distributed stable oxide particles(Y$$_{2}$$O$$_{3}$$). Properties and the tentative strength equations for ODS ferritic-martainsitic were proposed on the basis of the latest data to apply to the feasibility study of the sodium coolant MOX fuel plant. The items of equations are follows. (1)creep rupture strength (2)correction factor of creep rupture strength (in Na and in reactor) (3)outer surface eorrosion (Na) (4)inner surface corrosion (in MOX fuel pin) (5)thermal conductivity

Journal Articles

Creep properties with short period excessive loadings on a nickel-base heat-resistant alloy hastelloy XR

Tsuji, Hirokazu; *; *; Nakajima, Hajime

Journal of Nuclear Science and Technology, 31(4), p.274 - 278, 1994/04

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Creep properties with short period excessive loadings on a nickel-base heat-resistant alloy Hastelloy XR

Tsuji, Hirokazu; *; *; Nakajima, Hajime

JAERI-M 93-144, 69 Pages, 1993/07

JAERI-M-93-144.pdf:1.74MB

no abstracts in English

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