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社団法人 日本原子力学会 | 論文
- Improvement of Radiation Response Characteristic on CdTe Detectors using Fast Neutron Irradiation
- Development of an Atmospheric Dispersion Model for Accidental Discharge of Radionuclides with the Function of Simultaneous Prediction for Multiple Domains and its Evaluation by Application to the Chernobyl Nuclear Accident
- Measurements of keV-Neutron Capture Cross Sections and Capture Gamma-Ray Spectra of ^Dy
- Measurement of keV-Neutron Capture Cross Sections and Capture Gamma-Ray Spectra of ^Ce and ^Pr
- Development of Dust Removal System Using static Electricity for Fusion Experimental Reactors
- Numerical Analysis on Ingress of Coolant Event in Vacuum Vessel of Fusion Reactor Using Modified TRAC-BF1
- Improvement of Worldwide Version of System for Prediction of Environmental Emergency Dose Information (WSPEEDI), (I) : New Combination of Models, Atmospheric Dynamic Model MM5 and Particle Random Walk Model GEARN-new
- Improvement of Worldwide Version of System for Prediction of Environmental Emergency Dose Information (WSPEEDI), (II) : Evaluation of Numerical Models by ^Cs Deposition due to the Chernobyl Nuclear Accident
- Development of Three-Dimensional Numerical Model for ^Rn and Its Decay Products Coupled with a Mesoscale Meteorological Model II. Numerical Analysis on the Increase in Gamma Dose Rate Observed in the Coastal Area of Fukushima Prefecture
- Preliminary Estimation of Release Amounts of 131I and 137Cs Accidentally Discharged from the Fukushima Daiichi Nuclear Power Plant into the Atmosphere
- Measurement of keV-Neutron Capture Cross Sections and Capture Gamma-Ray Spectra of 167 Er
- Performance Test Results of Mock-up Test Facility of HTTR Hydrogen Production System
- LiNO_3 Effect on Corrosion Prevention of Aluminum with Complex Shapes
- Aluminum Corrosion under Alkaline Circumstances while LiN0_3 Concentration Is Lowered
- Uranium Crystallization Test with Dissolver Solution of Irradiated Fuel
- Separation of Actinide Elements by Solvent Extraction Using Centrifugal Contactors in the NEXT Process
- Uncertainty Evaluation of Effective Delayed Neutron Fraction β_ of Typical Proto-type Fast Reactor
- Development of Leak Detection System Using High Temperature-Resistant Microphones
- Evaluation of Delayed Neutron Data using FCA β_ Benchmark Experiment
- Physical and Chemical Properties of Solid Forms Fixing Heat-Generating Nuclides