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Allen, T.R.; Tsai, H.; Cole, J.I.; Yoshitake, T.; Akasaka, N.; Donomae, T.; Mizuta, S.; Ohta, J.; Dohi, K.; Kusanagi, H.
Abstracts of 2.Eurasian Conference on Nuclear Science and its Application2002
Abstracts of 2.Eurasian Conference on Nuclear Science and its Application2002
AbstractAbstract
[en] To assess the effects of long term, low dose rate neutron exposure on mechanical strength and ductility, tensile properties were measured on 12 % and 20 % cold worked (Cw) Type 316 stainless steel. Samples were prepared from reactor core components retrieved from the EBR-II reactor following final shutdown. Samples location were chosen to cover a dose range of 1-56 dpa at temperatures from 371-440 deg. C and dose rates from 0.5-5.8·10-7 dpa/s. These dose rates are about an order of magnitude lower than those of typical EBR-II test sample locations. The tensile properties and corresponding microstructural characterization data will be presented in this paper. For the 12 % CW Type 316 stainless steel at a dose of 40 dpa the yield strength measured at 430 deg. C increases by ∼33 % over that of the fresh material and does not appear to saturate. This increase in strength correlates with microstructural features associated with radiation hardening. The 20 % CW Type 316 stainless steel also hardens under irradiation. At the highest dose achieved (47 dpa), the total elongation is reduced to < 1 % and fracture mode appears to the transition from pure ductile rupture to a fracture with more brittle features. The work hardening ability of both materials decreases with dose at a similar rate. The swelling in both materials is too low to affect the ultimate tensile strength
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Ministry of Energy and Mineral Resources of the Republic of Kazakhstan, Astana (Kazakhstan); Atomic Energy Committee of the Republic of Kazakhstan, Almaty (Kazakhstan); Inst. of Nuclear Physics, Almaty (Kazakhstan); Nuclear Society of the Republic of Kazakhstan, Almaty (Kazakhstan); Engineering Academy of the Republic of Kazakhstan, Almaty (Kazakhstan); 482 p; ISBN 9185-2-X;
; 2002; p. 20-21; 2. Eurasian Conference on Nuclear Science and its Application; 2.Eurasian Conference on Nuclear Science and its Application; Almaty (Kazakhstan); 16-19 Oct 2002

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Book
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Conference
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ALLOYS, BARYONS, BREEDER REACTORS, CARBON ADDITIONS, DEFORMATION, ELEMENTARY PARTICLES, EPITHERMAL REACTORS, EXPERIMENTAL REACTORS, FABRICATION, FAST REACTORS, FBR TYPE REACTORS, FERMIONS, HADRONS, HARDENING, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, IRRADIATION, LIQUID METAL COOLED REACTORS, LMFBR TYPE REACTORS, MATERIALS WORKING, MECHANICAL PROPERTIES, NUCLEONS, PHYSICAL RADIATION EFFECTS, POWER REACTORS, RADIATION EFFECTS, REACTORS, RESEARCH AND TEST REACTORS, SODIUM COOLED REACTORS, STEELS, TENSILE PROPERTIES, TRANSITION ELEMENT ALLOYS
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