Journal of nuclear science and technology = 日本原子力学会英文論文誌

• 資料種別: 雑誌
• ISSN: 0022-3131
• ISSN-L: 0022-3131
• タイトル: Journal of nuclear science and technology
• タイトルよみ: Journal of nuclear science and technology
• 巻次・部編番号: 36(1)-36(6):1999.1-1999.6
• 著者標目: 日本原子力学会 ニホン ゲンシリョク ガッカイ ( 00280990 )典拠
• 出版事項: Tokyo : Atomic Energy Society of Japan
• 出版年月日等: 1999
• 出版年（W3CDTF）: 1999
• 刊行巻次・年月次: 1(1):1964.4 -
• 大きさ: 26-30cm
• 並列タイトル等: 日本原子力学会英文論文誌 ニホン ゲンシリョク ガッカイ エイブン ロンブンシ
• 出版地（国名コード）: JP
• 本文の言語コード: eng
• NDLC: ZM35
• 一般注記: Description based on the latest issue
• 所蔵機関: 国立国会図書館
• 請求記号: Z53-A460
• 関連情報: 区分換; https://ndlsearch.ndl.go.jp/books/R100000002-I024068116
• 連携機関・データベース: 国立国会図書館 : 国立国会図書館蔵書; https://ndlsearch.ndl.go.jp
• 書誌ID（NDLBibID）: 000000118776; http://id.ndl.go.jp/bib/000000118776
• 全国書誌番号: 10010902
• 目録規則: 国立国会図書館逐次刊行物目録規則
• 整理区分コード: 132

目次

Significance and Principal Features of Extended Driving Forces and a Transport Potential Model for Mass Transport between Two Liquids

Measurement of Fast Neutron-Induced Fission Cross Section Ratio of Neptunium-237 relative to Uranium-235 between 6 and 120keV

Possible Origin of the Gamma-ray Discrepancy in the Summation Calculations of Fission Product Decay Heat

Measurements of(n,xp),(n,xd)Double Differential Cross Sections of Carbon and Aluminum for 65 and 75MeV Neutrons

Numerical Simulation of an Expanding Pulsed Flow in a Laval Nozzle for the Molecular Laser Isotope Separation

Parallelization of the Hierarchical Domain Decomposition Boundary Element Method Applied to Multiregion Problem of Neutron Diffusion Equations

Experiment and Numerical Studies on Performance of Passive Decay Heat Removal by a Water Cooling Panel from a High-Temperature Gas-Cooled Reactor

Development of Simplified Wave-type Vane in BWR Steam Dryer and Assessment of Vane Droplet Removal Characteristics

Vapor Condensation and Thermophoretic Aerosol Deposition of Cesium Iodide in Horizontal Thermal Gradient Pipes

Evaluation of Leachable Behavior from Ion Exchange Resins:Effects of Organic Impurities on BWR Water Chemistry(1)

Evidence That There are Threshold Effects in Risk of Radiation

Assessment of Health Effect of Radioactivity Released from Donen-PNC Accident:Response of Japanese Journalism

A Movement to Discontinue Excessive Radiation Protection for Dental Patients

Recommendations for Promotion of Peaceful Uses of Nuclear Energy

Measurements of Neutron-induced Fission Cross Section o f Americium-243 from Thermal Neutron Energy to 15keV Using Lead Slowing-down Spectrometer and Thermal Neutron Facility

Current Status and Future Directions of Nuclear Education in Elementary and Secondary Education--Several Measures for Revitalization

Measurement of Thermal Neutron Capture Cross Section and Resonance Integral of the Reaction 127I(n,γ)128I

Measurement of Fisson Product Yields from Neutron-Induced Fisson of Americium-241

Benchmark Experiment on Vanadium with D-T Neutrons and Validation of Evaluated Nuclear Data Libraries by Analysis of the Experiment

Analysis of Neutron Spectra from Thick Targets Bombarded with 710-MeV Alpha Particles by Quantum Molecular Dynamics plus Statistical Decay Model

The 12C(p,p'3α)Breakup Reaction Induced by 14,18 and 26MeV Protons

Stopping Power Measurement of 225keV/u Oxygen Ions in Laser-Produced Lithium Hydride Plasma

Application of Neural Network to Multi-Dimensional Design Window Search in Reactor Core Design

Development of High Precision Plant Simulator for Pressurized Water Reactor Plants using Distributed Architecture

Dissolution Behavior of Pulverized Irradiated Fuels in Nitric Acid Solutions

Development of Core Diagnostic Methods and their Application at Swedish BWRs and PWRs

Measurement of Prompt Fission Neutron Spectrum of Neptunium-237 for 0.62MeV Incident Neutrons

Measurements of keV-Neutron Capture Cross Sections and Capture Gamma-Ray Spectra of 161,162,163Dy

Interface Waves Excited by Vertical Vibration of Stratified Fluids in a Circular Cylinder

The Occurrence of Wear Marks on Fast Reactor Fuel Pin Cladding