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Maziasz, P.J.; Braski, D.N.
Alloy development for irradiation performance. Semiannual progress report for period ending September 30, 19831984
Alloy development for irradiation performance. Semiannual progress report for period ending September 30, 19831984
AbstractAbstract
[en] Microstructural variants of PCA and two heats of 20%-cold-worked type 316 stainless steel were irradiated in HFIR and tested for embrittlement resistance with the disk-bend test. No embrittlement was observed for irradiation to approx. 44 dpa and 3000 to 3600 at. ppM He at 300 and 4000C. All materials were brittle after similar irradiation at 6000C. The test embrittlement resistance for irradiation to 44 dpa at 5000C and to 22 dpa at 6000C was found in PCA variants that contained grain boundary MC particles produced prior to irradiation
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Source
Oak Ridge National Lab., TN (USA); p. 60-65; Mar 1984; p. 60-65; Available from NTIS, PC A11/MF A01 as TI84007335
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Report
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ALLOYS, AUSTENITIC STEELS, BARYON REACTIONS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM-NICKEL STEELS, CORROSION RESISTANT ALLOYS, CRYSTAL STRUCTURE, ELEMENTS, ENRICHED URANIUM REACTORS, HADRON REACTIONS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, MOLYBDENUM ALLOYS, NICKEL ALLOYS, NONMETALS, NUCLEAR REACTIONS, NUCLEON REACTIONS, RARE GASES, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, STAINLESS STEELS, STEELS, TANK TYPE REACTORS, TEST REACTORS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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