Material test data of 2.25Cr-1Mo Steel and Mod.9Cr-1Mo Steel (Set of data)

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小高 進; 加藤 章一 ; 吉田 英一; 川上 朋広*; 鈴木 高一*; 高森 裕二*; 川島 成一*

Odaka, Susumu; not registered; Yoshida, Eiichi; not registered; not registered; not registered; not registered

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Matenal tests of 2.25Cr-1Mo Steel and Mod. 9Cr-1Mo Steel, which were used for structure material of fast breeder reactor (FBR) have been preformed in New Technology Development Group. In this report, the result of test obtained up to this time was collected. Many valuable data from long time test for more than 100000 hours including sodium environment test data in this report will be used for material examination of FBR in the future. It creates, in order for for ASME Code Committee to report this time. Contents of the data sheet are as follows; (1)Material: 2.25Cr-1Mo Steel and Mod.9Cr-1Mo Stee1 (2)Test environment: In air (3)Kind: Base metal (4)Heat treatment: Normalizing-tempering and stress relieving (5)Test temperature: 2.25Cr-1Mo Steel From 220 to 800deg Mod.9Cr-1Mo steel From 290 to 800deg (6)Test method: According to JIS and FBR Metallic Materials Test Manual (English version) (5)Number of data : 2.25Cr-1Mo Steel Creep tests 132 Fatigue tests 182 Creep-fatigue tests 66 Mod 9Cr-1Mo steel Creep tests 185 Fatigue tests 192 Creep-fatigue tests 27 Total 784 This report consists of the printouts from (the structural material data processing system,SMAT).