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Odaka, Susumu; Kato, Shoichi; Suzuki, Takaichi; Takamori, Yuji
Japan Nuclear Cycle Development Inst., Tokai, Ibaraki (Japan)2003
Japan Nuclear Cycle Development Inst., Tokai, Ibaraki (Japan)2003
AbstractAbstract
[en] Material test of SUS304 steel, which was used for structure material of fast breeder reactor (FBR) has been preformed in New Technology Development Group. In this report, the result of test obtained up to this time was collected. 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: SUS304 Steel, (2) Test environment: In air, in sodium, (3) Test temperature: Room temperature to 800degC, (4) Test method: According to JIS and FBR metallic materials test manual (revised edition), (5) Number of data: Tensile tests 1,185, Creep tests 1,044, Fatigue tests 1,037, Creep-fatigue tests 263, Total 3,529. This report consists of the printouts from 'the structural material data processing system, SMAT'. (author)
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Mar 2003; 959 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, JICST Service Homepage: www.jst.go.jp/EN/
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Report
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Numerical Data
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ALLOYS, AUSTENITIC STEELS, BREEDER REACTORS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM-NICKEL STEELS, CORROSION RESISTANT ALLOYS, DATA, EPITHERMAL REACTORS, FAST REACTORS, HEAT RESISTANT MATERIALS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, INFORMATION, IRON ALLOYS, IRON BASE ALLOYS, MATERIALS, MECHANICAL PROPERTIES, NICKEL ALLOYS, NUMERICAL DATA, REACTORS, STAINLESS STEELS, STEEL-CR19NI10, STEELS, TEMPERATURE RANGE, TRANSITION ELEMENT ALLOYS
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