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Tokai Research Establishment Japan Atomic Energy Research Institute | 論文
- Dose Delivered by Unit Amount of Tritium Released into the Environment
- Proton NMR Studies on Hydrogen-Doped Superconductor YBa_2Cu_3O_H_x : II-C Neutron Scattering, NMR and NQR and Ultrasonics : II Oxide Superconductors; Experiments II : Electronic States
- 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
- Distribution of CuO^+ in La_2CuO_y and La_Sr_CuO_y Pellets and Their Superconducting Properties
- Flow Pattern and Heat Transfer in Tube Banks of a Simulated Fluidized-Bed Heat Exchanger
- 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
- Spatially Resolved Electron Energy-loss Spectroscopy of the Surface Excitations on the Insulating Fine Particle of Aluminum Oxide : Condensed Matter: Electronic Properties, etc.
- Experimental Verification and Analysis of Neutron Streaming Effect through Void Holes for Control Rod Insertion in HTTR
- Photonuclear Angular Distribution Systematics in the Quasideuteron Regime
- Evaluation of Gamma-Ray Dose Components in Criticality Accident Situations
- Optical Parametric Oscillator with Periodically Poled KTiOPO_4 Pumped by 100 Hz Nd:YAG Green Laser : Optics and Quantum Electronics
- Crystal Distortion and Magnetic Structure of γ-MnM (M=Fe, Cu, Zn) Alloys
- Crystal Distortion and Magnetic Structure of γ-MnPd Alloys
- Crystal nucleation behavior caused by annealing of SiC irradiated with Ne at liquid nitrogen temperature or at 573K
- Recrystallization by annealing in SiC amorphized with Ne irradiation
- Soft-rotator Model Analysis of Collective Band Structures of Even-even Actinide Nuclei
- Creep Behavior of 8Cr2WVTa Martensitic Steel Designed for Fusion DEMO Reactor : An Assessment on Helium Embrittlement Resistance(Special Issue on Creep and Fatigue at Elevated Temperatures)