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Institute of Nuclear Technology Articles

Fatigue Life Prediction Model According to Crack Growth Concept (Fatigue Life Corrections for Loading History and Mean Stress Effects of S45C Carbonsteel)
Synergistic Effects of Ni and Si on the Formation of Solute Atom Clusters and Dislocation Loops in RPV Model Alloys
Evaluation of a phased array asymmetrical TOFD ultrasonic testing method by ultrasonic propagation simulation
SCC Initiation in Cold Worked Alloy 690 TT under Simulated PWR Primary Water（4th Report） – Growth Behavior of Microcracks –
SCC Growth Behavior of Stainless Steel Weld Metals in Oxygenated High-Temperature Water – Influence of Thermal Aging and Steel Type –
Microstructure and Fracture Behavior of Oxide Layers Formed on Irradiated Stainless Steel Weld Metal in Simulated PWR Primary Water
Influences of Dissolved Hydrogen on Corrosion Behavior of Alloy 690 TT in Zinc-Injected Simulated PWR Primary Water Condition（Part 2）
Study of the Irradiation Hardening Mechanism of Model Alloy of Reactor Pressure Vessel Steel Using Pop-in Phenomena
Second report of a trial analysis of licensee event reports（ LERs） of U.S. nuclear power plants by text mining
MAAP5 Analysis on TMI-2 Core Damage and Relocation in the Early Stages of the Accident
Application of Machine Learning Models for Statistical Safety Evaluation （Investigation of Applicability of Quantum Circuit Learning））
Numerical Simulation for Impinged Penetration Flow at a T-junction （Effect of Inlet Temperature Difference on Velocity and Temperature Distribution Characteristics）
Improvement of the Severe Accident Practice Tool
Development of an Evaluation Method Using Gaussian Process Regression for the Number of Steam Generator Tubes Broken

Document

On-site Survey on the Self-management of ECOTEC（Taikan Training）
Preliminary Study on the Reality of Hybrid Work
Trends in Public Opinion concerning Nuclear Power Generation in the United States and Europe after the Fukushima Daiichi Power Plant Accident（7）
The Interactive study session “After School Energy Talk” for Fukui Minami High School Asai Seminar students

Comments

Wall Condensation from Steam-Air Mixture in Forced Convection
Flow Characteristics in Vertical Pipes under Flooding Conditions

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