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Report No.

Creep test data of fuel cladding tube; Advanced austenitic stainless steels and high-nickel steel

not registered ; Yoshida, Eiichi; Sakurai, Tadashi*; Yaguchi, Katsumi*

In order to evaluation of high temperature creep strength, creep tests under internal pressure on the fuel cladding tube for fast breeder reactor (FBR) has been preformed in New Technology Development Group. In this report, the result of the creep and creep-rupture properties on the advance austenitic stainless and high-Ni steels obtained up to this time was collected. Valuable test data totals 149 points including sodium environment test data. These data will be reflected in development and design for fuel cladding material. Contents of the data sheet are as follows ; (1)Material and number of data: 15Cr-20Ni steel (2 heats) 72 points, PNC1520 steel (1 heats) 6 points, 14Cr-25Ni steel (8 heats) 56 points, High-Ni steel (1 heat) 15 points (2)Test environment : In-air, In-argon gas and In-sodium (3)Test temperature : 600$$^{circ}$$C to 750$$^{circ}$$C(873K to 1023K)



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