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検索キーワード:(著者名に左の語を含む: #GROSSBECK M.L.)
該当件数:35件
FATIGUE BEHAVIOR OF IRRADIATED HELIUM-CONTAINING FERRITIC STEELS FOR FUSION REACTOR APPLICATIONS. / GROSSBECK, M.L.(et al.)
, 1986. - (CONF ; CONF-860421-53)
レポート
IRRADIATION CREEP AT TEMPERATURES OF 400 (DEGREES)C AND BELOW FOR APPLICATION TO NEAR-TERM FUSION DEVICES. / GROSSBECK, M.L.(et al.)
, 1996. - (CONF ; CONF-960643-3; DE97002632)
EFFECT OF HELIUM ON IRRADIATION CREEP IN AN AUSTENITIC STAINLESS STEEL. / GROSSBECK, M.L.(et al.)
, 1987. - (CONF ; CONF-871101-58)
FATIGUE BEHAVIOR OF TYPE 316 STAINLESS STEEL FOLLOWING NEUTRON IRRADIATION INDUCING HELIUM. / GROSSBECK, M.L.
(CONF ; CONF-8009179-2)
FATIGUE PERFORMANCE OF HFIR-IRRADIATED NIMONIC PE-16 AT 430 DEG C. / GROSSBECK, M.L.
(CONF ; CONF-830942-27)
TENSILE AND FRACTURE PROPERTIES OF EBR-II-IRRADIATED V-15CR-5TI CONTAINING HELIUM. / GROSSBECK, M.L.(et al.)
, 1986. - (CONF ; CONF-860605-30)
FEASIBILITY OF CORRELATING V-CR-TI ALLOY WELD STRENGTH WITH WELD CHEMISTRY. CRADA FINAL REPORT (PROGRESS REPT). / GROSSBECK, M.L.(et al.)
: Oak Ridge National Laboratory(Oak Ridge National Laboratory) , 1998. - (ORNL ; ORNL/M-6554; DE98054346)
(RADIATION DAMAGE CORRELATION FOR FUSION CONDITIONS). / GROSSBECK, M.L.
: Oak Ridge National Laboratory(Oak Ridge National Laboratory) , 1989. - (ORNL ; ORNL/FTR-3409)
(LOW ACTIVATION ALLOYS FOR FUSION REACTORS). / GROSSBECK, M.L.
: Oak Ridge National Laboratory(Oak Ridge National Laboratory) , 1988. - (ORNL ; ORNL/FTR-3010)
(CONF ; CONF-800607-43)
IRRADIATION CREEP IN THE US FUSION ALLOY PCA AT FUSION HE/DPA LEVELS. / GROSSBECK, M.L.
, 1987. - (CONF ; CONF-8708138-5-VUGRAPHS)
IRRADIATION CREEP IN TYPE 316 STAINLESS STEEL AND US PCA WITH FUSION REACTOR HE/DPA LEVELS. / GROSSBECK, M.L.(et al.)
, 1987. - (CONF ; CONF-871036-9)
TENSILE PROPERTIES OF 20% COLD-WORKED TITANIUM-MODIFIEU TYPE 316 STAINLESS STEEL IRRADIATED IN HFIR. / GROSSBECK, M.L.
(CONF ; CONF-810831-95)
EFFECT OF IRRADIATION ON THE TENSILE PROPERTIES OF NIOBIUM-BASE ALLOYS. / GROSSBECK, M.L.(et al.)
, 1986. - (CONF ; CONF-870102-7)
SWELLING AND TENSILE PROPERTIES OF EBR-II-IRRADIATED TANTALUM ALLOYS FOR SPACE REACTOR. / GROSSBECK, M.L.(et al.)
, 1985. - (CONF ; CONF-850103-10)
FATIGUE BEHAVIOR AT 650 DEGREE OF 20%-COLD-WORKED TYPE 316 STAINLESS STEEL IRRADIATED AT 550 DEGREE IN THE HFIR. / GROSSBECK, M.L.(et al.)
, 1984. - (CONF ; CONF-840604-9)
TENSILE PROPERTIES OF TYPE 316 STAINLESS STEEL IRRADIATED IN A SIMULATED FUSION REACTOR ENVIRONMENT. / GROSSBECK, M.L.
(CONF ; CONF-790125-50)
TENSILE BEHAVIOR OF HELIUM-IMPLANTED AND NEUTRON-IRRADIATED V-15CR-5TI. / GROSSBECK, M.L.(et al.)
, 1986. - (CONF ; CONF-860610-18)
FISSION-REACTOR EXPERIMENTS FOR FUSION-MATERIALS RESEARCH. / GROSSBECK, M.L.
(CONF ; CONF-820406-13)
IN-REACTOR UNIAXIAL FRACTURE STRAIN OF 20%-COLD-WORKED TYPE 316 STAINLESS STEEL. / GROSSBECK, M.L.
(CONF ; CONF-830418-2-DRAFT)