Effect of cold work and slow strain rate on 321SS stress corrosion cracking in abnormal conditions of simulated PWR primary environment
Creators
- 1. China Institute of Atomic Energy, Peking, 102413 (China)
Description
In this paper, stress corrosion cracking (SCC) behavior of 0%, 5%, 10% cold-worked (CW) 321 stainless steel (321 SS) in abnormal conditions of simulated pressurized water reactor (PWR) primary water was studied at two different slow strain rates of 4.2 × 10−6, 4.2 × 10−7. The experimental results show that with the increase of the degree of cold work, the internal grain of the sample is refined. The slip zone and deformation twins occur inside some grains. The SCC sensitivity of the strain rate of 4.2 × 10−7 S−1 is higher than the strain rate of 4.2 × 10−6 S−1. And the higher the degree of cold work, the higher the SCC sensitivity of the sample. Dynamic strain aging (DSA) occurs at 321 SS with different cold work degrees with a slow strain rate of 4.2 × 10−7 S−1. DSA makes the tensile zone near the fracture of 5% CW and 10% CW samples have higher vacancy defect density, which promotes the initiation and expansion of SCC crack.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nme.2019.100697Additional details
Identifiers
- DOI
- 10.1016/j.nme.2019.100697;
- PII
- S2352179119300110;
Publishing Information
- Journal Title
- Nuclear Materials and Energy
- Journal Volume
- 20
- Journal Page Range
- vp.
- ISSN
- 2352-1791
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54120343
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTERIZED SIMULATION; CRACKING; DENSITY; FRACTURES; PWR TYPE REACTORS; STAINLESS STEEL-321; STRAIN AGING; STRAIN RATE; STRESS CORROSION; VACANCIES
- Descriptors DEC
- AGING; ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CORROSION; CORROSION RESISTANT ALLOYS; CRYSTAL DEFECTS; CRYSTAL STRUCTURE; DECOMPOSITION; ENRICHED URANIUM REACTORS; FAILURES; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; NICKEL ALLOYS; PHYSICAL PROPERTIES; POINT DEFECTS; POWER REACTORS; PYROLYSIS; REACTORS; SIMULATION; STAINLESS STEELS; STEEL-CR18NI10TI; STEELS; THERMAL REACTORS; THERMOCHEMICAL PROCESSES; TITANIUM ADDITIONS; TITANIUM ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2019 The Authors. Published by Elsevier Ltd.