Experiment and analysis on the creep-fatigue damage of a 316SS nonlinear structure in liquid metal reactor subjected to a cyclic loading with 1HR hold time
Creators
- 1. Korea Atomic Energy Research Institute (Korea, Republic of)
Description
The high temperature environment of the Liquid Metal Reactor (LMR) may cause the creep-fatigue damage in the reactor structures and it is important to be dealt with from a structural integrity point of view. This paper deals with the creep-fatigue damage evaluation of a typical geometrical discontinuity structure made of 316SS subjected to both a tensile loading and a high temperature loading. The creep-fatigue structural test of a cylindrical structure welded with a conical shell has been carried out with a 1MN IST actuator and a 50 kW induction heater with 1 hour hold time at 550 degree C. Total 400 cycles of testing were performed and the creep-fatigue damage in the discontinuous regions and the defect front, which were prepared by an electric discharge machining, were investigated using nondestructive methods. Also, the high temperature structural analysis program (NONSTA-VP) implementing Chaboche's unified viscoplasticity model into ABAQUS, developed to analyze creep-fatigue behavior, has been used to evaluate the creep-fatigue damage and the result has been compared with those of the structural test. The creep-fatigue crack initiation and growth behavior at the defect front were assessed and compared with the test results. (authors)
Additional details
Publishing Information
- Publisher
- Atomic Energy Press
- Imprint Place
- Beijing (China)
- ISBN
- 7-5022-3421-7
- Imprint Title
- Proceedings of 18th international conference on structural mechanics in reactor technology
- Imprint Pagination
- 4896 p.
- Journal Page Range
- p. 4638-4646
Conference
- Title
- 18. international conference on structural mechanics in reactor technology
- Dates
- 7-12 Aug 2005
- Place
- Beijing (China)
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 43021763
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- A CODES; C CODES; COMPUTER CODES; CRACK PROPAGATION; CYLINDRICAL CONFIGURATION; ELECTRIC DISCHARGES; EVALUATION; FATIGUE; HEATERS; LIQUID METAL COOLED REACTORS; MACHINING; N CODES; NONLINEAR PROBLEMS; PLASTICITY; STAINLESS STEEL-316; TEMPERATURE RANGE 0400-1000 K; TENSILE PROPERTIES; TESTING; TIME DEPENDENCE
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-MOLYBDENUM STEELS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STEELS; COMPUTER CODES; CONFIGURATION; CORROSION RESISTANT ALLOYS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MECHANICAL PROPERTIES; MOLYBDENUM ALLOYS; NICKEL ALLOYS; REACTORS; STAINLESS STEELS; STEEL-CR17NI12MO3; STEELS; TEMPERATURE RANGE; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 18 figs., 3 tabs., 20 refs.