The influence of cold-work level on the irradiation creep and swelling of AISI 316 stainless steel irradiated as pressurized tubes in the EBR-II fast reactor
Creators
- 1. Pacific Northwest National Laboratory, P.O. Box 999, M/S P8-15 Richland, WA 99354 (United States)
Description
Pressurized tubes of AISI 316 stainless steel irradiated in the P-1 experiment in the EBR-II fast reactor have been measured to determine the dependence of irradiation-induced strains resulting from plastic deformation, irradiation creep, void swelling and precipitation. It is shown that the Soderberg relation predicting no axial creep strains in biaxially-loaded tubes is correct for both plastic and creep strains. Swelling strains are shown to be isotropically distributed both for stress-free and stress-affected swelling, while precipitation strains are somewhat anisotropic in their distribution. When corrected for stress-enhancement of swelling, the derived irradiation creep strains appear to be identical for both annealed and 20% cold-worked specimens, and also for tubes strained by rise to power increases in pressure. For relatively small creep strains it is often difficult to separate the creep and non-creep components of deformation
Additional details
Identifiers
- DOI
- 10.1016/j.jnucmat.2007.03.059;
- PII
- S0022-3115(07)00517-X;
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 367-370
- Journal Page Range
- p. 954-959
- ISSN
- 0022-3115
- CODEN
- JNUMAM
Conference
- Title
- 12. international conference on fusion reactor materials
- Acronym
- ICFRM-12
- Dates
- 7-12 Dec 2005
- Place
- Santa Barbara, CA (United States)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 39010022
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANNEALING; CREEP; EBR-2 REACTOR; IRRADIATION; PHYSICAL RADIATION EFFECTS; PLASTICITY; STAINLESS STEEL-316L; STRAINS; STRESSES; SWELLING; VOIDS
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; BREEDER REACTORS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-MOLYBDENUM STEELS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STEELS; CORROSION RESISTANT ALLOYS; DEFORMATION; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HEAT TREATMENTS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; LOW CARBON-HIGH ALLOY STEELS; MATERIALS; MECHANICAL PROPERTIES; MOLYBDENUM ALLOYS; NICKEL ALLOYS; POWER REACTORS; RADIATION EFFECTS; REACTORS; RESEARCH AND TEST REACTORS; SODIUM COOLED REACTORS; STAINLESS STEELS; STEEL-CR17NI12MO3-L; STEELS; TRANSITION ELEMENT ALLOYS
Optional Information
- Copyright
- Copyright (c) 2007 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.