A review of some effects of helium on Charpy impact properties of ferritic/martensitic steels
Creators
- 1. Battelle Pacific Northwest Labs., Richland, WA (United States)
- 2. Loughborough Univ. of Technology (United Kingdom). Inst. of Polymer Technology and Materials Engineering
Description
To evaluate the effect of helium on Charpy impact properties of ferritic/martensitic steels, two approaches are reviewed: quantification of results of earlier tests performed by other researchers on specimens irradiated in reactors with very different neutron spectra, and evaluation of isotopic tailoring experiments. Data analysis can show that if the differences in reactor response are indeed due to helium effects, then irradiation in a fusion machine at 400 C to 100 dpa and 1000 appm He will result in a ductile-to-brittle transition temperature (DBTT) shift of over 500 C. However, it can be shown that the response as a function of dose and helium level is unlikely to be simply due to helium based on physical reasoning. Shear punch tests and microstructural examination support this conclusion based on irradiated samples of a series of alloys made by adding various isotopes of nickel in order to vary the production of helium during irradiation in high flux isotope reactor (HFIR). The addition of nickel at any isotopic balance to the Fe-12Cr base alloy significantly increased the shear yield and maximum strengths of the alloys. However, helium itself, up to 75 appm at over 7 dpa appears to have little effect on the mechanical properties of the alloys. This behavior is instead understood to result from complex precipitation response. The database for effects of helium on embrittlement based on nickel additions is therefore probably misleading and experiments should be redesigned to avoid nickel precipitation. (orig.)
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 258-263
- Journal Issue
- pt.B
- Journal Page Range
- p. 1216-1221
- ISSN
- 0022-3115
- CODEN
- JNUMAM
Conference
- Title
- 8. international conference on fusion reactor materials (ICFRM-8)
- Dates
- 26-31 Oct 1997
- Place
- Sendai (Japan)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 30005428
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BUBBLES; CHARPY TEST; DUCTILE-BRITTLE TRANSITIONS; EMBRITTLEMENT; FERRITIC STEELS; FISSION NEUTRONS; HELIUM; HFIR REACTOR; MARTENSITIC STEELS; NEUTRON SPECTRA; NICKEL ADDITIONS; PRECIPITATION; RADIATION EFFECTS; SHEAR PROPERTIES; TEMPERATURE RANGE 0273-0400 K; TEMPERATURE RANGE 0400-1000 K; THERMONUCLEAR REACTOR MATERIALS; TRANSMISSION ELECTRON MICROSCOPY; VOIDS; YIELD STRENGTH
- Descriptors DEC
- ALLOYS; BARYONS; CARBON ADDITIONS; DESTRUCTIVE TESTING; ELECTRON MICROSCOPY; ELEMENTARY PARTICLES; ELEMENTS; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; IMPACT TESTS; IRON ALLOYS; IRON BASE ALLOYS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MATERIALS; MATERIALS TESTING; MECHANICAL PROPERTIES; MECHANICAL TESTS; MICROSCOPY; NEUTRONS; NONMETALS; NUCLEONS; RARE GASES; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SEPARATION PROCESSES; SPECTRA; STEELS; TANK TYPE REACTORS; TEMPERATURE RANGE; TEST FACILITIES; TEST REACTORS; TESTING; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 9 refs.