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Research Reactor Institute, Kyoto University | 論文
- Analysis of the Angular Distribution and the Intensity of Parametric X-Ray Radiation in a Bragg Case
- Isolation of Novel Peptides, Cabin-1, -2, -3, and -4, That Inhibit Cathepsin B from a Thermolysin Digest of Human Plasma
- A Review of Research Activities at the Research Reactor Institute of Kyoto University in View of Research Publication Information
- Determination of Chemical Form of Antimony in Contaminated Soil around a Smelter Using X-ray Absorption Fine Structure
- Measurements of Reaction Rate Ratios as Indexes of Breeding Performance in Mock-up Cores of FCA Simulating Metallic-fueled LMFBR and MOX-fueled LMFBR
- ^P-Retention of DNA irradiated in a Reactor The Enhancement of the Retention with Increasing Irradiation Time
- Nuclear Design Study on a Super High-burnup Fuel Assembly for Pressurized Water Reactors Using Transuranium
- 冷中性子ラジオグラフィ-を用いたLi1.33Ti1.67O4中のリチウムイオンの動きの解析
- Analysis of Experiment on Temperature Coefficient of Reactivity in Light-Water-Moderated and Heavy-Water-Reflected Cylindrical Core Loaded with Highly-Enriched-Uranium or Medium-Enriched-Uranium Fuel
- Experimental Study on Temperature Coefficient of Reactivity in Light-Water-Moderated and Heavy-Water-Reflected Cylindrical Core Loaded with Highly-Enriched-Uranium or Medium-Enriched-Uranium Fuel
- 中性子ラジオグラフィによるリチウム電池内におけるリチウム元素分布の可視化〔英文〕
- Measurement and Analysis of Leakage Neutron Spectrum from a Spherical Pile of Silicon with Incident 14MeV Neutrons
- Measurement of Leakage Neutron Spectra from a Spherical Pile of Zirconium Irradiated with 14MeV Neutrons and Validation of Its Nuclear Data
- Measurement of Leakage Neutron Spectra from a Spherical Pile of Niobium Bombarded with 14MeV Neutrons and Validation of Its Nuclear Data
- easurement and Analysis of Leakage Neutron Spectra from Spherical Assemblies of Chromium, Manganese and Copper with 14MeV Neutrons
- Measurements of Neutron-induced Fission Cross Section of Protactinium-231 from 0. 1eV to 10keV with Lead Slowing-down Spectrometer and at 0. 0253eV with Thermal Neutron Facility
- Measurements of Neutron-induced Fission Cross Section of Americium-243 from Thermal Neutron Energy to 15keV Using Lead Slowing-down Spectrometer and Thermal Neutron Facility
- Excitation of 6^+, 8^+ 10^+ and 9^- States in ^Sn by Reactions (p,t) and (p,p')
- TED-AJ03-389 IMPROVED MEASUREMENT METHOD FOR INTERFACIAL AREA CONCENTRATION IN A LARGE DIAMETER TUBE
- Detection of Polynuclear Zirconium Hydroxide Species in Aqueous Solution by Desktop ESI-MS