Dependence of mechanical properties on swelling in austenitic steels
Creators
- 1. Texas A and M Univ., College Station, TX (United States). Dept. of Nuclear Engineering
- 2. Argonne National Lab., Idaho, ID (United States)
Description
The effect of swelling on the behavior of reactor materials is an important concern for the performance and lifetime extension issues of nuclear reactors. Austenitic steels are the main structural material in fast reactors and they are widely employed also in light water reactor systems. Material property data concerning austenitic steels of EBR-II and BN350 fast reactors has been compiled. The Russian austenitic steels show strong correlation of ultimate tensile strength and total elongation with swelling over a large swelling range. Some assemblies from BOR-60 reactor also support these findings (1). For American steels, the changes in the strength and ductility with neutron exposure and swelling have been investigated in some detail. However, most of these studies are confined to modest amounts of swelling where there may be only limited correlation with mechanical properties (2,3). Therefore, the data on Russian austenitic steels is of great importance to understand the mechanical property behavior of austenitic steels over a large range of swelling (or dose) and to apply these findings to the light water reactor systems considering exposure temperature, dose rate and neutron energy spectrum differences. (author)
Additional details
Publishing Information
- Publisher
- Japan Society of Mechanical Engineers
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- ICONE-11: Proceedings of the 11th international conference on nuclear engineering
- Imprint Pagination
- [3610 p.]
- Journal Page Range
- [7 p.]
Conference
- Title
- 11. international conference on nuclear engineering
- Acronym
- ICONE-11
- Dates
- 20-23 Apr 2003
- Place
- Tokyo (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 35073078
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AUSTENITIC STEELS; BN-350 REACTOR; BUILDING MATERIALS; EBR-2 REACTOR; ELONGATION; NEUTRON FLUX; PHYSICAL RADIATION EFFECTS; RADIATION DOSES; REACTOR MATERIALS; SWELLING; TEMPERATURE DEPENDENCE; TEMPERATURE RANGE 1000-4000 K; TENSILE PROPERTIES
- Descriptors DEC
- ALLOYS; BREEDER REACTORS; CARBON ADDITIONS; DEFORMATION; DESALINATION REACTORS; DOSES; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; IRON ALLOYS; IRON BASE ALLOYS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS; MECHANICAL PROPERTIES; POWER REACTORS; RADIATION EFFECTS; RADIATION FLUX; REACTORS; RESEARCH AND TEST REACTORS; SODIUM COOLED REACTORS; STEELS; TEMPERATURE RANGE; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Track No. 11, Session 11-8, ICONE-36464