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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 and rupture behavior of hastelloy XR in simulated HTGR helium

*; Kurata, Yuji; ; Nakajima, Hajime; Kondo, Tatsuo

Nihon Genshiryoku Gakkai-Shi, 36(10), p.967 - 975, 1994/00

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

no abstracts in English

JAEA Reports

The Effect of Helium on Mechanical Properties of Cladding During a LOCA

;

JAERI-M 5749, 14 Pages, 1974/06

JAERI-M-5749.pdf:0.8MB

no abstracts in English

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