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

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Evaluation Methods for Corrosion Damage of Components in Cooling Systems of Nuclear Power Plants by Coupling Analysis of Corrosion and Flow Dynamics (IV) : Comparison of Wall Thinning Rates Calculated with the Coupled Model of Static Electrochemical Analy
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
Evaluation of Effectiveness of Hydrogen Water Chemistry for Different Types of Boiling Water Reactors
ICONE11-36145 SSRT FACILITY FOR IN-SITU OBSERVATION IN HIGH TEMPERATURE WATER OF IRRADIATED MATERIALS
Applicability of Chemical Cleaning Process to Steam Generator Secondary Side, (III) : Effect of Chemical Cleaning on Long Term Integrity of Steam Generator Tube after Chemical Cleaning Process
Applicability of Chemical Cleaning Process to Steam Generator Secondary Side, (II) : Effect of Chemical Cleaning on Integrity of SG Tubing under Accelerated IGSCC Conditions
Applicability of Chemical Cleaning Process to Steam Generator Secondary Side, (I) Outline of the Investigation and Cleaning Effectiveness
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
Applicability of Chemical Cleaning Process to Steam Generator Secondary Side, (IV) : Comprehensive Applicability Evaluation of Chemical Cleaning and Its Effect on Integrity of Other Structural Materials Other than Steam Generator Tubes
Revised Procedure for Determining Large Excess Reactivity of Reactors
Creep Properties under Varying Stress/Temperature Conditions on Nickel-Base Heat-Resistant Alloy Hastelloy XR

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