LOW-CYCLE FATIGUE AND HOLD TIME COMPARISONS OF IRRADIATED AND UNIRRADIATED TYPE-316 STAINLESS-STEEL

[1] BEESTON JM, 1971, STP484 ASTM AM SOC T, P419

[2] Brinkman C. R., 1973, Symposium on Effects of Radiation on Substructure and Mechanical Properties of Metals and Alloys, P473

[3] ESTIMATES OF CREEP-FATIGUE INTERACTION IN IRRADIATED AND UNIRRADIATED AUSTENITIC STAINLESS-STEELS [J]. NUCLEAR TECHNOLOGY, 1972, 16 (01) : 297 - &

[4] BRINKMAN CR, 1973, ANCR1097 AER NUCL CO

[5] CHENG CF, 1973, STP520 ASTM PUBL, P355

[6] DAWSON RAT, 1967, THERMAL HIGH STRAIN

[7] TENSILE PROPERTIES OF ANNEALED TYPE-316 STAINLESS-STEEL AFTER EBR-II IRRADIATION [J]. JOURNAL OF NUCLEAR MATERIALS, 1973, 46 (02) : 113 - 120

[8] JASKE CE, 1972, REACTOR TECHNOL, V15

[1] BEESTON JM, 1971, STP484 ASTM AM SOC T, P419

[2] Brinkman C. R., 1973, Symposium on Effects of Radiation on Substructure and Mechanical Properties of Metals and Alloys, P473

[3] ESTIMATES OF CREEP-FATIGUE INTERACTION IN IRRADIATED AND UNIRRADIATED AUSTENITIC STAINLESS-STEELS [J]. NUCLEAR TECHNOLOGY, 1972, 16 (01) : 297 - &

[4] BRINKMAN CR, 1973, ANCR1097 AER NUCL CO

[5] CHENG CF, 1973, STP520 ASTM PUBL, P355

[6] DAWSON RAT, 1967, THERMAL HIGH STRAIN

[7] TENSILE PROPERTIES OF ANNEALED TYPE-316 STAINLESS-STEEL AFTER EBR-II IRRADIATION [J]. JOURNAL OF NUCLEAR MATERIALS, 1973, 46 (02) : 113 - 120

[8] JASKE CE, 1972, REACTOR TECHNOL, V15