Stress corrosion cracking of neutron irradiated type 304 stainless steels
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)
- 2. Japan Atomic Energy Research Inst., Tokyo (Japan)
Description
To study the effect of minor elements on the irradiation assisted stress corrosion cracking (IASCC), a high purity type 304L stainless steel and its heats doped minor elements, Si, P, S, C and Ti were irradiated at 513 K to 6.7 x 1024 n/m2 (E>1 MeV). After irradiation, susceptibility to the stress corrosion cracking (SCC) was evaluated by the slow strain rate tensile (SSRT) test in an oxygenated high purity water at 573 K, and the fracture surface of the specimens was examined by the scanning electron microscopy (SEM). The specimens showed high susceptibilities to SCC. Specimens without addition of C showed the intergranular type SCC (IGSCC), while C doped specimens generally failed by the transgranular type SCC (TGSCC). Addition of C into the hi purity alloy caused an enhancement of radiation hardening and a remarkable increase in maximum stress during SSRT test. Enrichment of Si changed specifically tensile properties after irradiation and decreased maximum stress and improved total elongation. Addition of S greatly enhanced the IASCC susceptibility and addition of P seemed to be beneficial for suppressing it. An effect of Ti was not prominent in the alloy with a high C concentration
Additional details
Publishing Information
- Publisher
- NACE International.
- Imprint Place
- Houston, TX (United States)
- ISBN
- 1-877914-95-9
- Imprint Title
- Seventh international symposium on environmental degradation of materials in nuclear power systems -- Water reactors: Proceedings and symposium discussions. Volume 2
- Imprint Pagination
- 620 p.
- Journal Page Range
- p. 1009-1018.
Conference
- Title
- water reactors.
- Acronym
- 7. NACE international symposium on environmental degradation of materials in nuclear power plants
- Dates
- 6-10 Aug 1995.
- Place
- Breckenridge, CO (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27043648
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- CARBON; CRACK PROPAGATION; EXPERIMENTAL DATA; MECHANICAL TESTS; METALLURGICAL EFFECTS; PHOSPHORUS; PHYSICAL RADIATION EFFECTS; REACTOR MATERIALS; SILICON; STAINLESS STEEL-304L; SULFUR; TITANIUM; WATER COOLED REACTORS
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CORROSION RESISTANT ALLOYS; DATA; ELEMENTS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; LOW CARBON-HIGH ALLOY STEELS; MATERIALS; MATERIALS TESTING; METALS; NICKEL ALLOYS; NONMETALS; NUMERICAL DATA; RADIATION EFFECTS; REACTORS; SEMIMETALS; STAINLESS STEELS; STEEL-CR19NI10-L; STEELS; TESTING; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENTS
Optional Information
- Secondary number(s)
- CONF-950816--.