Published December 2021 | Version v1
Journal article Metadata-only

Crack initiation of neutron-irradiated 304 L stainless steel in PWR primary water

Creators

  • 1. Department of Nuclear Engineering and Radiological Sciences, University of Michigan, 2355 Bonisteel Blvd., Ann Arbor, MI 48109 (United States)
  • 2. Yangtze Delta Research Institute, Northwestern Polytechnical University, 27 Zigang Road, Taicang, Jiangsu 215400 (China)
  • 3. Department of Materials Science and Engineering, University of Michigan, 2355 Bonisteel Blvd., Ann Arbor, MI 48109 (United States)

Description

Highlights: • 304 L showed no strong IASCC dependence on dose in the range of 5.4–125.4 dpa. • Crack initiated at stresses well below yield with a stress threshold of 0.5σy. • Grain boundary oxidation is a necessary step of crack initiation. • Dislocation channels formed at stresses below yield and enhanced GB oxidation. Stress corrosion crack (SCC) initiation of neutron-irradiated 304 L stainless steel was studied following irradiation to various doses. Tensile test results show that SCC susceptibility dependence of the alloy on dose is slight. Grain boundary (GB) oxidation was observed prior to crack initiation and DCs always proceeded before or accompanies crack initiation in the bend test. The DC-GB intersections were the predominant crack initiation sites due to the high local stress. Constant load tests resulted in greater GB oxidation and cracks initiated at applied stress as low as 50% of the irradiated yield strength due to the long exposure time.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.corsci.2021.109902

Additional details

Identifiers

DOI
10.1016/j.corsci.2021.109902;
PII
S0010938X21006685;

Publishing Information

Journal Title
Corrosion Science
Journal Volume
193
Journal Page Range
vp.
ISSN
0010-938X
CODEN
CRRSAA

INIS

Country of Publication
United Kingdom
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
54018898
Subject category
S36: MATERIALS SCIENCE; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
ATOMIC DISPLACEMENTS; CRACK PROPAGATION; DISLOCATIONS; GRAIN BOUNDARIES; IRRADIATION; NEUTRONS; OXIDATION; PWR TYPE REACTORS; STAINLESS STEELS; STRESS CORROSION; STRESSES; YIELD STRENGTH; YIELDS
Descriptors DEC
ALLOYS; BARYONS; CARBON ADDITIONS; CHEMICAL REACTIONS; CORROSION; CRYSTAL DEFECTS; CRYSTAL STRUCTURE; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; LINE DEFECTS; MECHANICAL PROPERTIES; MICROSTRUCTURE; NUCLEONS; PHYSICAL RADIATION EFFECTS; POWER REACTORS; RADIATION EFFECTS; REACTORS; STEELS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Copyright
Copyright (c) 2021 Elsevier Ltd. All rights reserved.