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Pugh, C.E.; Purdy, C.M.
Oak Ridge National Lab., Tenn. (USA); Energy Research and Development Administration, Washington, D.C. (USA)1977
Oak Ridge National Lab., Tenn. (USA); Energy Research and Development Administration, Washington, D.C. (USA)1977
AbstractAbstract
[en] A statement is given of material properties information needed in connection with the structural design technology for liquid-metal fast breeder reactor (LMFBR) primary circuit components. Implementation of current analysis methods and criteria is considered with an emphasis on data and data correlations for performing elastic-plastic and creep analyses, for establishing allowable stress limits, and for computing creep-fatigue damage. Further development of the technology is discussed in relation to properties information. Emphasis is placed on improved constitutive equations for representing inelastic material behavior, on procedures for treating time-dependent fatigue, and on criteria for creep rupture. The properties are generally discussed without regard to specific alloys, since most categories of information are needed for each major structural material. Some sample experimental results are given for type 304 stainless steel and 21/4 Cr-1 Mo steel
Primary Subject
Secondary Subject
Source
1977; 46 p; International working group on fast reactors (IAEA/IWGFR) specialists meeting; Bensburg, Germany, F.R; 17 - 21 Oct 1977; Available from NTIS., PC A03/MF A01
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
ALLOYS, BREEDER REACTORS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM STEELS, CHROMIUM-NICKEL STEELS, COOLING SYSTEMS, CORROSION RESISTANT ALLOYS, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, HEAT RESISTING ALLOYS, IRON ALLOYS, IRON BASE ALLOYS, LIQUID METAL COOLED REACTORS, MOLYBDENUM ALLOYS, NICKEL ALLOYS, REACTOR COMPONENTS, REACTOR COOLING SYSTEMS, REACTORS, STAINLESS STEELS, STEELS, TRANSITION ELEMENT ALLOYS
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