INFLUENCE OF MEAN STRESS AND PWR ENVIRONMENT ON FATIGUE BEHAVIOR OF A 304L SS

Gespeichert in:
Bibliographische Detailangaben
Veröffentlicht in:International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors (19. : 2019 : Boston, Mass.) 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors 2019 ; Volume 2 of 2
1. Verfasser: Peng, Z. (VerfasserIn)
Weitere Verfasser: Henaff, G. (VerfasserIn), Roux, J. C. Le (VerfasserIn), Verlet, R. (VerfasserIn)
Pages:19
Format: UnknownFormat
Sprache:eng
Veröffentlicht: 2020
Schlagworte:
Tags: Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
Titel Jahr Verfasser
MODELING THE EVOLUTION OF INTERGRANULAR HELIUM BUBBLES IN NICKEL USING THE INCLUDED PHASE MODEL 2020 Prudil, A. A.
MICROSTRUCTURE OF NI AND X-750 IRRADIATED AT LOW AND HIGH TEMPERATURES 2020 Li, W.
EFFECT OF PROTON-INDUCED RADIOLYSIS ON CORROSION OF 316L STAINLESS STEEL IN SIMULATED PWR PRIMARY WATER 2020 Hanbury, R. D.
UNDERSTANDING THE MECHANISMS OF SURFACE AND CRACK TIP OXIDATION WITH VALENCE MAPPING 2020 Lozano-Perez, S.
CABLE AGING AND CM APPROACHES BEYOND THE SHORTCOMINGS OF IAEA NUCLEAR ENERGY SERIES NO. NP-T-3.6 2020 Gillen, K. T.
"MIND THE GAP" BETWEEN OLD AND NEW NUCLEAR QUALIFIED CABLE: LESSONS LEARNED FROM AGING, HISTORICAL ADVERSE EVENTS AND OTHER NUCLEAR CABLE ISSUES 2020 Cunningham, L.
THE DETERMINATION OF THE REACTION RATES, WATER VAPOR PERMEABILITY, AND ACTIVATION ENERGY FOR THERMAL OXIDATION OF LDPE FILMS 2020 Munir, N.
EFFECTS OF AGING TEMPERATURE AND ALLOY COMPOSITION ON LONG-RANGE ORDERING IN NI-CR-FE ALLOYS DURING ISOTHERMAL AGING 2020 Ru, X.
DEGRADATION EFFECTS OF HYDROGEN AND HIGH-TEMPERATURE WATER ENVIRONMENTS ON THE FRACTURE RESISTANCE OF LOW-ALLOY RPV STEELS 2020 Que, Z.
EFFECTS OF GAMMA RAY IRRADIATION ON CORROSION OF CARBON STEEL AT WATER LINE 2020 Ariga, T.
EFFECT OF STRAIN AND STRAIN RATE ON CRACK INITIATION OF 316L STEEL IN THE SIMULATION PWR WATER 2020 Hajna, lbu A.
THE STRESS INTENSITY FACTOR DEPENDENCE OF 304 STAINLESS STEEL SCC GROWTH IN DEAERATED WATER 2020 Morton, D.
3D CHARACTERIZATION OF CORROSION FATIGUE CRACKS AND CRACK TIPS GENERATED IN TYPE 304/304L STAINLESS STEEL DURING ENHANCED AND RETARDED FATIGUE CRACK GROWTH 2020 Anglin, B. S.
HYDROGEN ASSISTED OXIDATION BEHAVIOR OF ALLOY 600 IN HIGH TEMPERATURE AIR ENVIRONMENT BY IN-SITU H CHARGING METHOD 2020 Wang, Z.
EMPIRICAL EQUATIONS OF CRACK GROWTH RATES BASED ON DATA FITTING OF NEUTRON IRRADIATED STAINLESS STEEL UNDER HIGH TEMPERATURE WATER SIMULATING BOILING WATER REACTOR CORE CONDITIONS 2020 Kasahara, S.
ON THE POTENTIAL SYNERGIES OF HELIUM AND HYDROGEN ON THE NUCLEATION AND STABILITY OF CAVITY CLUSTERS IN INCONEL X-750 30 IRRADIATED IN A HIGH THERMAL NEUTRON FLUX SPECTRA 2020 Judge, C. D.
OXIDATION CHARACTERISTICS OF NI-CR-FE ALLOY SYSTEMS IN SIMULATED PWR PRIMARY WATER: EFFECT OF CR CONTENT 2020 Hur, H. S. Shim. D. H.
SMALL SCALE TENSILE TESTING OF GRAIN BOUNDARY STRENGTH OF X-750 ALLOY 2020 He, L.
THE INFLUENCE OF METAL SUBSTRATE ON CRUD BUILD-UP UNDER SIMULATED PWR CONDITIONS 2020 Cassineri, S.
COUPLING EFFECT OF CHARGED-HYDROGEN AND COLD WORK ON OXIDATION BEHAVIOR OF 316L STAINLESS STEEL IN DEAERATED HIGH TEMPERATURE WATER 2020 Cui, T.
Alle Artikel auflisten