Crack growth behavior of warm-rolled 316L austenitic stainless steel in high-temperature hydrogenated water
Creators
- 1. Department of Nuclear Science and Engineering, School of Mechanical and Nuclear Engineering, Ulsan National Institute of Science and Technology (UNIST), 50 UNIST-gil, Eonyang-eup, Ulju-gun, Ulsan 44919 (Korea, Republic of)
- 2. Nuclear Materials Safety Research Division, Korea Atomic Energy Research Institute (KAERI), 111, Daedeok-daero 989beon-gil, Yuseong-gu, Daejeon 34057 (Korea, Republic of)
Description
To investigate the effects of warm rolling on the crack growth of 316L austenitic stainless steel, the crack growth rate was measured and the oxide structure was characterized in high-temperature hydrogenated water. The warm-rolled specimens showed a higher crack growth rate compared to the as-received specimens because the slip bands and dislocations produced during warm rolling served as paths for corrosion and cracking. The crack growth rate increased with the dissolved hydrogen concentration. This may be attributed to the decrease in performance and stability of the protective oxide layer formed on the surface of stainless steel in high-temperature water. - Highlights: • 316L Stainless steels were used for the study of crack growth behavior in PWR water. • Warm rolling was applied to simulate the irradiation hardening of stainless steels. • DH concentration was changed to see the effect on crack growth and oxide structure. • Warm-rolled stainless steels showed higher rates of corrosion and crack growth. • Higher DH concentration also promoted the rates of corrosion and crack growth.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.jnucmat.2016.04.051Additional details
Identifiers
- DOI
- 10.1016/j.jnucmat.2016.04.051;
- PII
- S0022-3115(16)30173-8;
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 476
- Journal Page Range
- p. 243-254
- ISSN
- 0022-3115
- CODEN
- JNUMAM
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48037213
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPARATIVE EVALUATIONS; CONCENTRATION RATIO; CORROSION; CRACK PROPAGATION; CRACKING; CRACKS; DISLOCATIONS; HYDROGEN; HYDROGENATION; IRRADIATION; LAYERS; OXIDATION; OXIDES; PWR TYPE REACTORS; ROLLING; SLIP; STAINLESS STEEL-316L; TEMPERATURE RANGE 0400-1000 K; TRANSMISSION ELECTRON MICROSCOPY; WATER
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHALCOGENIDES; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-MOLYBDENUM STEELS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STEELS; CORROSION RESISTANT ALLOYS; CRYSTAL DEFECTS; CRYSTAL STRUCTURE; DECOMPOSITION; DIMENSIONLESS NUMBERS; ELECTRON MICROSCOPY; ELEMENTS; ENRICHED URANIUM REACTORS; EVALUATION; FABRICATION; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; HYDROGEN COMPOUNDS; IRON ALLOYS; IRON BASE ALLOYS; LINE DEFECTS; LOW CARBON-HIGH ALLOY STEELS; MATERIALS; MATERIALS WORKING; MICROSCOPY; MOLYBDENUM ALLOYS; NICKEL ALLOYS; NONMETALS; OXYGEN COMPOUNDS; POWER REACTORS; PYROLYSIS; REACTORS; STAINLESS STEELS; STEEL-CR17NI12MO3-L; STEELS; TEMPERATURE RANGE; THERMAL REACTORS; THERMOCHEMICAL PROCESSES; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.