A study on the 430 deg C degradation behavior of cast stainless steel(CF8M) (2) -Evaluation of low cycle fatigue characteristics -
- 1. Yeungnam Univ., Taegu (Korea, Republic of)
- 2. Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)
Description
A thermal aging is observed in a primary reactor cooling system(RCS) made of a casting stainless steel when the RCS is exposed for long period at the reactor operating temperature, 290-330 deg C. An investigation of effects of thermal aging on a low cycle fatigue characteristics included a stress variations caused by a reactor operation and trip, is required. The purpose of the present investigation is to find an effect of a thermal aging of the CF8M on a low cycle fatigue life. The specimen of CF8M are prepared by an artificially accelerated aging technique holding 300 and 1800hr at 430 deg C respectively. The low cycle fatigue tests for the virgin and two aged specimens are performed at the room temperature for various strain amplitudes(ε ta), 0.3, 0.5, 0.8, 1.0, 1.2, and 1.5% strain. Through the experiment, it is found that the fatigue life is rapidly reduced with an creasing of the aging time. The experimental fatigue life estimation formulas between the virgin and two aged specimen are obtained and are proposed to a analysis purpose
Additional details
Publishing Information
- Journal Title
- Transactions of the Korean Society of Mechanical Engineers. A
- Journal Volume
- 24
- Journal Issue
- 9
- Series
- 18 refs, 9 figs, 2 tabs
- Journal Page Range
- p. 2183-2190
- ISSN
- 1226-4873
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 31058050
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- AGING; CASTING; HARDENING; REACTOR COOLING SYSTEMS; STAINLESS STEELS; STRAINS; THERMAL ANALYSIS; THERMAL DEGRADATION; THERMAL FATIGUE
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; COOLING SYSTEMS; ENERGY SYSTEMS; FABRICATION; FATIGUE; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; REACTOR COMPONENTS; STEELS; TRANSITION ELEMENT ALLOYS