NONDESTRUCTIVE EVALUATION OF CONCRETE SPECIMENS REPRESENTATIVE OF NUCLEAR POWER PLANTS CONTAINING KNOWN DEFECTS

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 1 of 2
1. Verfasser: Ezell, N. D. B. (VerfasserIn)
Weitere Verfasser: Albright, A. (VerfasserIn), Floyd, D. (VerfasserIn), Khazanovich, L. (VerfasserIn)
Pages:19
Format: UnknownFormat
Sprache:eng
Veröffentlicht: 2020
Schlagworte:
Tags: Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
Titel Jahr Verfasser
EFFECT OF WELDING DILUTION AND DENDRITE ORIENTATION ON SCC BEHAVIOR OF ALLOY 52M WELDING METAL IN SIMULATED PWR PRIMARY WATER 2020 Ma, J.
INFLUENCE OF LONG-TERM THERMAL AGING ON SCC INITIATION SUSCEPTIBILITY OF L-GRADE AUSTENITIC STAINLESS STEEL 2020 Kondo, K.
EFFECT OF UV IRRADIATION ON CORROSION BEHAVIOR OF ZIRCONIUM ALLOY IN HIGH TEMPERATURE WATER CONDITIONS 2020 Kim, T.
EFFECT OF THERMAL AGING ON MICROSTRUCTURE AND HARDNESS OF INDUSTRIAL HEATS OF ALLOY 690 2020 Huotilainen, C.
NEXT GENERATION OF NOBLE METAL APPLICATION FOR BOILING WATER REACTORS 2020 Gianelli, J.
IMPACT OF CORROSION OF NICKEL BASED COATINGS FOR FLOW ACCELERATED CORROSION CONTROL ON BWR RADIATION FIELDS 2020 Jarvis, A. J.
BIAXIAL CREEP OF TEXTURED ZR-NB ALLOYS 2020 Joshi, P.
NON-DESTRUCTIVELY DETECTING LWR STRUCTURAL MATERIAL EMBRITTLEMENT USING TRANSIENT GRATING SPECTROSCOPY 2020 Dajani, S. A. Al
STEAM OXIDATION, BURST AND CRITICAL HEAT FLUX TESTING OF COMMERCIAL FECRAL CLADDING 2020 Pint, B:A.
CORROSION BEHAVIOUR OF PHYSICAL VAPOUR DEPOSITED COATINGS ON NUCLEAR COMPONENTS AND FE-CR-AL ALLOY UNDER NORMAL OPERATION AND ACCIDENT SCENARIOS 2020 Dever, C.
STRESS CORROSION CRACKING OF A286 REACTOR COOLANT PUMP TURNING VANE BOLTS 2020 Ickes, M. R.
AN INVESTIGATION INTO THE CORROSION BEHAVIORS OF STAINLESS STEEL AND NI- BASED ALLOY IN SIMULATED PWR PRIMARY WATER ENVIRONMENTS 2020 Chang, C. J.
DESIGN AND FABRICATION OF ALLOY A-286 FOR RESISTANCE TO IGSCC IN PWRS 2020 Fyfitch, S.
EMPIRICAL EQUATIONS FOR TENSILE PROPERTIES AND STRESS-STRAIN CURVES OF NEUTRON IRRADIATED STAINLESS STEELS IN LWR CONDITIONS 2020 Fukuya, K.
THE EFFECT OF DIFFUSION-INDUCED GRAIN BOUNDARY MIGRATION AHEAD OF SCC CRACK TIPS ON PROPAGATION . 2020 Shen, Z.
UNDERSTANDING THE ROLE OF GRAIN BOUNDARY MIGRATION ON THE INITIATION STAGES OF PWSCC 2020 Volpe, L.
REVIEW OF RADIATION INDUCED DEGRADATION OF CONCRETE STRUCTURE IN COMMERCIAL NUCLEAR POWER PLANTS AROUND REACTOR VESSEL 2020 Biwer, B.
NUCLEAR CONCRETE MICROSTRUCTURE GENERATION FOR SIMULATING CREEP 2020 Torrence, C. E.
INVESTIGATING THE ROLE OF HYDROGEN ON STRESS CORROSION CRACKING BY MICROMECHNAICAL TESTING 2020 Roberts, E.
EXPERIMENTAL DESIGN TO STUDY THE MECHANICAL PERFORMANCE OF IRRADIATED ACRYLONITRILE BUTADIENE STYRENE FABRICATED VIA FUSED FILAMENT FABRICATION 2020 Miller, A. J.
Alle Artikel auflisten