ICONE11-36145 SSRT FACILITY FOR IN-SITU OBSERVATION IN HIGH TEMPERATURE WATER OF IRRADIATED MATERIALS
スポンサーリンク
概要
著者
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TSUJI Hirokazu
Japan Atomic Energy Research Institute
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TSUKADA Takashi
Japan Atomic Energy Agency
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Nakano Junichi
Japan Atomic Energy Agency
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UGACHI Hirokazu
Japan Atomic Energy Agency
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Kohya Toshio
Japan Atomic Energy Research Institute (JAERI)
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Endo Shinya
Japan Atomic Energy Research Institute (JAERI)
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Tsuji Hirokazu
Department Of Nuclear Energy System Japan Atomic Energy Research Institute
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Tsukada Takashi
Department Of Nuclear Energy System Japan Atomic Energy Research Institute
関連論文
- Multiaxial Creep Behavior of Nickel-Base Heat-Resistant Alloys Hastelloy XR and Ni-Cr-W Superalloy at Elevated Temperatures
- SB-02-2(075) Multiaxial Creep Behavior of Nickel-Base Heat-Resistant Alloys Hastelloy XR and Ni-Cr-W Superalloy at Elevated Temperatures(Materials Performance in Nuclear Application 2)
- Effects of Hydrogen Peroxide on Corrosion of Stainless Steel, (V) Characterization of Oxide Film with Multilateral Surface Analyses
- ICONE11-36145 SSRT FACILITY FOR IN-SITU OBSERVATION IN HIGH TEMPERATURE WATER OF IRRADIATED MATERIALS
- Development of a Filler Metal for Weldments of a Ni-Cr-W Superalloy with High Creep Strength(Special Issue on Creep and Fatigue at Elevated Temperatures)
- SB-02-1(064) Development of a filler metal for weldments of a Ni-Cr-W superalloy with high creep strength(Materials Performance in Nuclear Application 2)
- In-Core SCC Growth Behavior of Type 304 Stainless Steel in BWR Simulated High-Temperature Water at JMTR
- ICONE11-36136 Program of in-pile IASCC testing under the simulated actual plant condition : Development of Technique for In-pile IASCC Initiation Test in JMTR
- ICONE11-36119 PROGRAM OF IN-PILE IASCC TESTING UNDER THE SIMULATED ACTUAL PLANT CONDITION : Development of technique for in-pile IASCC growth test in JMTR
- ICONE11-36106 Program of in-pile IASCC testing under the simulated actual plant condition : Thermohydraulic design study of saturated temperature capsule for IASCC irradiation test
- Creep Properties of Base Metal and Welded Joint of Hastelloy XR Produced for High-Temperature Engineering Test Reactor in Simulated Primary Coolant Helium
- ICONE11-36324 Program of in-pile IASCC testing under the simulated actual plant condition : Overview
- ICONE11-36111 Stress corrosion cracking susceptibility of thermally sensitized type 304 stainless steels doped with various levels of carbon and silicon
- ICONE11-36107 Stress corrosion cracking susceptibility of thermally sensitized type 304 stainless steels doped with various levels of carbon and silicon
- ICONE11-36093 AFM EVALUATION FOR CORROSION BEHAVIOR OF ION IRRADIATED STAINLESS STEEL
- Development of Analytical Method and Study about Microstructure of Oxide Films on Stainless Steel
- Status of JAERI Material Performance Database(JMPD)and Analysis of Irradiation Assisted Stress Corrosion Cracking(IASCC)Data
- Creep Properties under Varying Stress/Temperature Conditions on Nickel-Base Heat-Resistant Alloy Hastelloy XR