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Onizawa, Takashi; Kato, Shoichi
Japan Nuclear Cycle Development Inst., Tokai, Ibaraki (Japan)2001
Japan Nuclear Cycle Development Inst., Tokai, Ibaraki (Japan)2001
AbstractAbstract
[en] Material test of 2.25Cr-1Mo steel, which was used for steam generator of fast breeder reactor (FBR) has been preformed in Structure Safety Engineering Group. Many valuable data that long time test more than 100000 hours including sodium environment test data in this report will be use for material examination of FBR in the future. Contents of the data sheet are as follows; (1) Material: 2.25Mr-1Mo Steel. (2) Test environment: In air, in sodium. (3) Test temperature: room temperature to 1000degC. (4) Test method: According to JIS and FBR Metallic Materials Test Method. (5) Number of data: Tensile tests 713, Creep tests 450, Fatigue tests 330, Creep-fatigue tests 108, Relaxation tests 61, Total 1662. This report consists of the printouts from 'the structural material data processing system, SMAT'. (author)
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Source
Mar 2001; 614 p; Available from JICST Library (JICST: Japan Science and Technology Corporation, Information Center for Science and Technology), P.O. Box 10 Hikarigaoka, Tokyo 179-9810 Japan, FAX: +81-3-3979-4781 (domestic), FAX: +81-3-3979-2210 (oversea); 148 figs.
Record Type
Report
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Numerical Data
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ALLOYS, BREEDER REACTORS, CHROMIUM ALLOYS, CHROMIUM STEELS, DATA, EPITHERMAL REACTORS, FAST REACTORS, HIGH ALLOY STEELS, INFORMATION, IRON ALLOYS, IRON BASE ALLOYS, JOINTS, MATERIALS, MECHANICAL PROPERTIES, MOLYBDENUM ALLOYS, NUMERICAL DATA, REACTORS, STAINLESS STEELS, STEELS, TEMPERATURE RANGE, TESTING, TRANSITION ELEMENT ALLOYS
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