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Creep-damage evaluation of modified 9Cr-1Mo steel based on a time-fraction concept

Conference ·
OSTI ID:136870
 [1];  [2];  [3];  [4]
  1. Toshiba Corp., Yokohama (Japan). Nuclear Engineering Lab.
  2. Japan Atomic Power Co., Tokyo (Japan). Fast Breeder Reactor Development Dept.
  3. Mitsubishi Heavy Industries, Ltd., Takasago (Japan). Takasago Research and Development Center
  4. Hitachi, Ltd. (Japan). Advanced Reactor and Nuclear Fuel Cycle Dept.
+ Show Author Affiliations
In the elevated-temperature design guide (DDS) for the Japanese demonstration fast breeder reactor (DFBR), a time-fraction concept is applied to creep-damage evaluation based on an analytical stress-relaxation behavior calculated from the creep properties. Modified 9Cr-1Mo steel is the most likely structural material for the steam generator of the DFBR. For this material, the creep damage calculated by the conventional time-fraction rule based on the experimental stress-relaxation behavior was inappropriately small in previous studies. The authors reported that the time-fraction approach modified by the creep properties after cyclic softening is able to evaluate creep damage fairly well. In this paper, the time-fraction concept based on the analytical stress-relaxation behavior with the cyclic stress strain relation (the DDS approach) is applied to the evaluation of creep-fatigue test results, demonstrating that the DDS approach can suitably estimate the creep damage. It is also shown that the DDS approach can approximately match the creep damage as calculated based on the creep strength after cyclic softening.
OSTI ID:
136870
Report Number(s):
CONF-950740--; ISBN 0-7918-1344-4
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
CREEP
DATA
DATA ANALYSIS
DEMONSTRATION PROGRAMS
FBR TYPE REACTORS
JAPAN
MECHANICAL TESTS
REACTOR MATERIALS
RUPTURES
STEAM GENERATORS
STEEL-CR9MO