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List of Jounal Titles
A to Z index of Journal Title. Choose a letter.
Transactions of the Atomic Energy Society of Japan
5
- Numerical Analysis of Turbulent Flow Separation in a Rectangular Duct with Sharp 180-Degree Turn
- Liquid Film Thickness on Fuel Rod under High Pressure and High Temperature Steam-Water Two Phase Flow
- Development of a Fluorination Decontamination Technique for Uranium Bearing Waste
- Analysis of Mixed Oxide Fuel Critical Experiments EPICURE and MISTRAL with Nuclear Analysis Code for BWR
- Improvement of Core Dynamics Analysis of Control Rod Withdrawal Test in HTGR
- Evaluation of Fuel Temperature on High Temperature Test Operation at High Temperature Gas-Cooled Reactor 'HTTR'
- Development of Sulfuric Acid Decomposer for Thermochemical Hydrogen Production IS Process
- Design Development of Thermoelectric Generator by Design Engineering
2
- Core Dynamics Analysis of Control Rod Withdrawal Test and Nuclear Characteristics in HTTR: Reactor Power 30-60%
- Numerical Analysis of CCFL in Perforated Thick Plate using Extended Two-Fluid Model
- Fluorination of Uranium and Plutonium Dioxides in Flame Tower Reactors
- Economical Evaluation on Gas Turbine High Temperature Reactor 300 (GTHTR300)
- Development of Seismic Load Evaluation Code for Evaluating Structural Reliability of Nuclear Components
- Development of Probabilistic Safety Assessment Method for Mixed Oxide Fuel Fabrication Facilities
- Issues on the Physical Protection Scheme from the Viewpoint for Realizing Effective Evaluation
- Analysis and Study of Spent Fuel Reprocessing Technology from Birth to Present
3
- Development of a Simple Method for Classifying the Degree of Importance of Components in Nuclear Power Plants using Probabilistic Analysis Technique
- Experimental Investigation of Characteristics of Impinging Jet Heat Transfer and Application to JSNS Moderator Design
- Reduction of Temperature Changes in Heat Transfer Fluid by the Use of Latent Heat Storage Technology
- Seismic Fragility Capacity of Equipment: Horizontal Shaft Pump Test
- Radiation Degradation of Microchemical Chips and Capillary Tubes by Gamma-Ray Irradiation
- Usability of a New Multiple High-speed Pulse Time Data Registration, Processing and Real-time Display System for Pulse Time Interval Analysis
- Development of a Source Term Estimation Method for Nuclear Emergency by Long-range Atmospheric Dispersion Simulations
- Assessment of Calculation Model for Annular Core on the HTTR
4
- Development of the Package-Reactor
- Reaction Analysis of MOX Co-deposition in Oxide Electrowinning Process
- Trending Analysis of Incidents Involving Primary Water Stress Corrosion Cracking on Alloy 600 Components at U.S. PWRs
- Evaluation of Hydrogen Production System Coupling with HTTR Using Dynamic Analysis Code
- Uncertainty Evaluation of Source Terms under Severe Accident Conditions at LWRs
- Analysis on Characteristic of Hydrogen Gas Dispersion and Evaluation Method of Blast Overpressure in VHTR Hydrogen Production System
- Safety Design Philosophy of Hydrogen Cogeneration High Temperature Gas Cooled Reactor (GTHTR300C)
- Application of Probabilistic Safety Assessment to Rokkasho Reprocessing Plant, (I) The Occurrence Frequency of Loss of Hydrogen Scavenging Function in Plutonium Solution Vessel
- Corrosion Test of Structural Materials for Thermo-Chemical and Electrolytic Hybrid Hydrogen Production Cycle
- Cost Estimation of Uranium Recovery from Seawater with System of Braid Type Adsorbent
- Development of Chemical Decontamination Technique Using Formic Acid
- Radon Emanation Phenomena: Previous Studies and Future Outlook
1
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