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Wakai, E.; Hashimoto, N.; Gibson, L.T.
Fusion materials semiannual progress report for period ending June 30, 19971997
Fusion materials semiannual progress report for period ending June 30, 19971997
AbstractAbstract
[en] The microstructural evolution of austenitic JPCA aged and solution annealed JPCA, 316R, C, K, and HP steels irradiated at 400 degrees C in spectrally tailored experiments of the ORR and HFIR has been investigated. The helium generation rates were about 12-16 appm He/dpa on the average up to 17.3 dpa. The number densities and average diameters of dislocation loops in the steels have ranges of 3.3 x 1021 m-3 and 15.2-26.3 nm, respectively, except for HP steel for which they are 1.1 x 1023 m-3 and 8.0 nm. Precipitates are formed in all steels except for HP steel, and the number densities and average diameters have ranges of 5.2 x 1020 - 7.7 x 1021 m-3 and 3.4- 19.3 nm, respectively. In the 216R, C, and K steels, the precipitates are also formed at grain boundaries, and the mean sizes of these are about 110, 50, and 50 nm, respectively. The number densities of cavities are about 1 x 1022 m-3 in all the steels. The swelling is low in the steels which form the precipitates
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Oak Ridge National Lab., TN (United States); 358 p; Aug 1997; p. 159-168; Also available from OSTI as DE97008797; NTIS; US Govt. Printing Office Dep
Record Type
Report
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Progress Report
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ALLOYS, CARBON ADDITIONS, CLOSED PLASMA DEVICES, CRYSTAL STRUCTURE, DEFORMATION, DOCUMENT TYPES, IRON ALLOYS, IRON BASE ALLOYS, MATERIALS, NEUTRON FLUENCE, RADIATION EFFECTS, STEELS, THERMONUCLEAR DEVICES, THERMONUCLEAR REACTOR WALLS, THERMONUCLEAR REACTORS, TOKAMAK DEVICES, TOKAMAK TYPE REACTORS, TRANSITION ELEMENT ALLOYS
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