INTERFACE CHARACTERIZATION OF CANDIDATE DUAL-PURPOSE BARRIER COATINGS FOR SIC/SIC ACCIDENT TOLERANT FUEL CLADDING

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: Kabel, J. (VerfasserIn)
Weitere Verfasser: Koyanagi, T. (VerfasserIn), Katoh, Y. (VerfasserIn), Schoell, R. (VerfasserIn), Kaoumi, D. (VerfasserIn), Ang, C. (VerfasserIn), Hosemann, P. (VerfasserIn)
Pages:19
Format: UnknownFormat
Sprache:eng
Veröffentlicht: 2020
Schlagworte:
Tags: Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
Titel Jahr Verfasser
IMPACT OF THE STARTUP TEMPERATURE AND PRIMARY CHEMISTRY PROGRAM ON THE OXIDATION AND RELEASE OF CORROSION PRODUCTS FROM ALLOY 690 STEAM GENERATOR 2020 Flambard, J.
SPATIAL RESOLUTION OF A CABLE FAULT LOCATION ATTEMPT BY FREQUENCY DOMAIN REFLECTOMETRY 2020 Ohki, Y.
MICROSTRUCTURAL CHARACTERIZATION OF STEAM GENERATOR TUBE FLAKES FROM AN OPERATING PWR AND ITS GALVANIC CORROSION BEHAVIOR 2020 Jeon, S. H.
ELECTRICAL BREAKDOWN STRENGTH AND AC WITHSTAND IN HARVESTED EPR INSULATIONS FOR NUCLEAR POWER PLANTS 2020 Duckworth, R.
EFFECTS OF DRY, WET-DRY CYCLING AND AQUEOUS IMMERSION ON POLYPROPYLENE AND POLYETHYLENE CABLE INSULATION MECHANICAL PROPERTIES 2020 Salinas, I.
MICROSTRUCTURAL CHARACTERIZATION OF REACTOR CAVITY CONCRETE 2020 Arregui-Mena, J. D.
DEVELOPMENT OF MO-FREE LOW ALLOY STEELS FOR MITIGATION OF FLOW- ACCELERATED CORROSION IN SECONDARY SIDE OF PWRS 2020 Kim, S.
STRESS ASSESSMENT OF BAFFLE FORMER BOLT OF PWR REACTOR FOR IASCC 2020 Pandit, A. M.
INVESTIGATING PB-INDUCED STRESS CORROSION CRACKING OF ALLOY 800 VIA IN- SITU XPS 2020 Payne, B.
MICROSTRUCTURAL CHARACTERIZATION OF ALLOY 690TT EXPOSED TO PB- CONTAINING CAUSTIC SOLUTIONS 2020 Mazzei, G. B.
UNDERSTANDING THE EFFECT OF STRAIN LOCALIZATION ON CORROSION FATIGUE OF TYPE 304 AUSTENITIC STAINLESS STEELS IN HIGH TEMPERATURE WATER 2020 Wang, H.
IASCC INITIATION TEST OF NEUTRON IRRADIATED TYPE 316L STAINLESS STEEL IN SIMULATED BWR CONDITION TO EVALUATE THRESHOLD STRESS 2020 Chatani, K.
IASCC SUSCEPTIBILITY OF HIGHLY IRRADIATED 316 STAINLESS STEEL IN SIMULATED PWR PRIMARY WATER 2020 Du, D.
SPECIMEN SIZE EFFECTS ON THE CRACK GROWTH RATE RESPONSE OF HIGHLY IRRADIATED TYPE 304 STAINLESS STEEL 2020 Jenssen, A.
USING A MULTI-SCALE APPROACH TO ASSESS THE MECHANICAL PROPERTIES AND DEFORMATION MECHANISMS OF HIGH DOSE INCONEL X-750 2020 Howard, C.
LOCAL OXIDATION PENETRATION OF HYDROGEN-CHARGED 308L STAINLESS STEEL CLADDING IN DEAERATED PWR PRIMARY WATER 2020 Cui, T.
COMBINED APPROACH TO MEDIUM VOLTAGE CABLE AND ACCESSORIES AGING MANAGEMENT TECHNIQUE AT NUCLEAR POWER PLANTS 2020 Khondker, R.
NUCLEAR ELECTRICAL PENETRATOR ASSEMBLIES AND CONNECTORS FOR SMALL MODULAR AND OTHER ADVANCED REACTORS 2020 Kumar, P.
CHARACTERISTICS OF OXIDE FILMS FORMED ON 309L AND 308L STAINLESS STEELS IN SIMULATED PWR PRIMARY WATER 2020 Xiong, Q.
PARAMETER SENSITIVITY OF INTERDIGITAL SENSORS FOR THEIR DESIGN FOR CABLE INSULATION AGING DETECTION 2020 Al-Imran, M. N.
Alle Artikel auflisten