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Tokai Research Establishment, Japan Atomic Energy Research Institute | 論文
- Oxidation of Fuel Rod under Dry Storage Condition
- High Temperature Doppler Effect Experiment for ^U at FCA, (II) Reaction Rate Measurement up to 2, 000℃ with a Foil Heated by Laser Exposure
- High Temperature Doppler Effect Experiment for ^U at FCA, (I) Reactivity Worth Measurement with a Small Heated Sample up to 1, 500℃
- Anthropogenic Radionuclides in Seawater of the Japan Sea : The Results of Recent Observations and the Temporal Change of Concentrations
- Lead-Bismuth Eutectic Compatibility with Materials in the Concept of Spoliation Target for ADS(International Conferences on Power and Energy System)
- Electron Energy Loss Spectroscopy on Oxygen K-Edge Fine Structure of YBa_2Cu_3O_y Containing Dopants (La, Ca, Co)
- Oxygen K-Edge Fine Structure of Tl_1Ba_2Ca_Cu_nO_ Studied by Electron Energy Loss Spectroscopy
- Experimental Study on Heat Transfer Augmentation for High Heat Flux Removal in Rib-Roughened Narrow Channels
- Effect of Flow Field on Colloid Deposition in Filtration Process of Polystyrene Latex Particles through Columns Packed with Glass Beads
- Dose Delivered by Unit Amount of Tritium Released into the Environment
- A8 A TWIN OPTICALLY-PUMPED FAR-INFRARED CH_3OH LASER FOR THE LARGE TOKAMAK PLASMA DIAGNOSTICS
- Magnetization of Ceramic Y-Ba-Cu-O and Bi-Sr-Ca-Co-O after Neutron Irradiation
- Critical Current and Activation Energy in Bi_2Sr_2Ca_1Cu_2O_x Films after Ion Irradiation
- Irradiation Behavior of developed radiaiton resistance optical-fibers and observed optical radiation from their SiO_2 cores under reactor irradiation
- Distribution of CuO^+ in La_2CuO_y and La_Sr_CuO_y Pellets and Their Superconducting Properties
- Study on Creep-Fatigue Life of Irradiated Austenitic Stainless Steel(Special Issue on Creep and Fatigue at Elevated Temperatures)
- SB-01-3(098) Study on Creep-Fatigue Life of Irradiated Austenitic Stainless Steel(Materials Performance in Nuclear Application 1)
- Effects of Neutron Irradiation on Tensile Properties in High-Purity Fe-(9-50) Cr and Fe-50Cr-xW Alloys
- Experimental Verification and Analysis of Neutron Streaming Effect through Void Holes for Control Rod Insertion in HTTR
- Crud Behaviors in High Temperature Water, (II) : Characterization of Corrosion Layer on Type 304 Stainless Steel and Zircaloy-2