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Japan Nuclear Cycle Development Institute | 論文
- ICONE11-36598 Conceptual Design of a Medium Scale Lead-Bismuth Cooled Fast Reactor
- Evaluation of β-γ Coincidence Measurement System Using Plastic Scintillation β-ray Detector Developed for the Determination of γ-ray Emission Probabilities of Short-lived Nuclides
- Measurement of Effective Neutron Capture Cross Section of ^Ho using Two Step Irradiation Technique
- Prediction of Release Rate of Burnt Sodium as Aerosol
- Reflection and Diffraction Phenomena of Blast Wave Propagation in Nuclear Fuel Cycle Facility(International Conferences on Power and Energy System)
- ICONE11-36092 Reflection and Diffraction Phenomena of Blast Wave Propagation in Nuclear Fuel Cycle Facility
- Transmutation of Technetium in the Experimental Fast Reactor "JOYO"
- Environmental Gamma-Ray Dose Rate in Aomori Prefecture
- Investigation of physicochemical form of uranium in sediment of brackish Lake Obuchi using sequential extraction procedure
- Characteristics of fluctuations in salinity and water quality in brackish Lake Obuchi
- Fuel Channel Inspection Equipment for RBMK Reactors
- Numerical Approach to the Safety Evaluation of Sodium-Water Reaction
- ICONE11-36526 PSA APPLICATION ON THE TOKAI REPROCESSING PLANT
- Fabrication and Thermal Conductivity of Boron Carbide/Copper Cermet
- Resonance Self-Shielding Corrections for Activation Cross Section Measurements
- Thermal Conductivities of Granular UO_2 Compacts with/without Uranium Particles
- Geostatistical and geochemical classification of groundwaters considered in safety assessment of a deep geologic repository for high-level radioactive wastes in Japan
- ICONE11-36191 RADIATION ACTIVITY EVALUATION FOR DECOMMISSIONING OF FUGEN NUCLEAR POWER STATION
- Applicability of Thermodynamic Database of Radioactive Elements Developed for the Japanese Performance Assessment of HLW Repository
- Analysis of Overheating Rupture in Heat-Transfer Tubes Causing Corrosive High-Temperature Reaction