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Japan Atomic Energy Res. Inst. | 論文
- Evaluation of Neutron Nuclear Data for Mercury
- Japanese Evaluated Nuclear Data Library Version 3 Revision-2 : JENDL-3. 2
- Measurements of Reaction Rate Ratios as Indexes of Breeding Performance in Mock-up Cores of FCA Simulating Metallic-fueled LMFBR and MOX-fueled LMFBR
- Thermal Expansion and Thermal Conductivity of Cesium Uranates
- Density, Porosity and Grain Size, (II) Irradiated ROX Fuels to Burn-up of 28%FIMA
- Density, Porosity and Grain Size, (I) Unirradiated ROX Fuels
- Behavior of Nb_2O_5 Doped/Unpressurized UO_2 Fuel under Transient
- New cystoscopic diagnosis for interstitial cystitis/painful bladder syndrome using narrow-band imaging system
- Experimental Study on Heat Transfer Augmentation for High Heat Flux Removal in Rib-Roughened Narrow Channels
- Failure to detect Mycoplasma genitalium in the pharynges of female sex workers in Japan
- Equilibrium of Nitrous Acid-Catalyzed Oxidation of Neptunium in Nitric Acid-TBP Extraction System
- Evaluation of Nertron-and Proton-induced Nuclear Data on ^Al up to 2GeV
- Dose Delivered by Unit Amount of Tritium Released into the Environment
- Development of a High Intensity RFQ at JAERI
- Updated Japanese Urological Association Guidelines on prostate-specific antigen-based screening for prostate cancer in 2010
- Evidence-based clinical practice guidelines for bladder cancer (Summary - JUA 2009 Edition)
- A questionnaire survey of patient preparation and techniques for prostate biopsy among urologists in the Kyushu and Okinawa regions of Japan
- Measurement and Analysis of Fission Rate Distributions of ^Np and ^U in a Polyethylene System with a 65 MeV Neutron Source
- Nuclear Medium Effects in the Intranuclear Cascade Calculation
- Experimental and Theoretical Investigations on Heat Transfer of Strongly Heated Turbulent Gas Flow in an Annular Duct