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: 40(1)-40(6):2003.1-2003.6(P.1-446)
• 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: 2003
• 出版年（W3CDTF）: 2003
• 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

Measurement of keV-Neutron Capture Cross Sections and Capture Gamma-Ray Spectra of 99Tc

Analysis of Nucleon scattering Data of 52Cr with a Coupling Scheme Built with the Son-rotator Model

Effect of Higher-Harmonic Flux in Exponential Experiment for Subcriticality Measurement

Magnetically Guided Free Surface Annular NaK Flow Experiment

Numerical Simulation of Non-Premixed Diffusion Flame and Reaction Product Aerosol Behavior in Liquid Metal Pool Combustion

Measurement of the Thermal Neutron Capture Cross Section and the Resonance Integral of the 109Ag(n, γ) 110mAg Reaction

Analysis of Subcooled Boiling with the Two-Fluid Particle Interaction Method

Shapes and Rising Velocities of Single Bubbles rising through and Inner Subchannel

Synergy Effect of Simultaneous Zinc and Nickel Addition on Cobalt Deposition onto Stainless Steel in Oxygenated High Temperature Water

Signal Fluctuation and Neutron Source in Inverse Kinetics Method for Reactivity Measurement in the Sub-critical Domain

Neutron-Production Double-Differential Cross Sections of Iron and Lead by 0.8 and 1.5 GeV Protons in the Most-Forward Direction

The Analytic Function Expansion Nodal(AFEN) Method with Half-Interface Averaged Fluxes in Mixed Geometry Nodes for Analysis of Pebble Bed Modular Reactor(PBMR) Cores

Control of a High Temperature Supercritical Pressure Light Water Cooled and Moderated Reactor with Water Rods

Numerical Simulation of Aerosol Behavior in Turbulent Natural Convection--Verification of an Advanced Model

Off-take and Slug Transition at T-junction of Vertical-up Branch in the Horizontal Pipe

Systems Analysis of Spent Fuel Management in Japan(1)Projection of Material Balances and Storage Needs

Systems Analysis of Spent Fuel Management in Japan(2)Methodologies for Economic Analyses of Spent Fuel Storage

Calculation of Gamma-Ray Buildup Factors up to Depths of 100 mfp by the Method of Invariant Embedding(2)Improved Treatment of Bremsstrahlung

Development of Kinetics Model for BWR Core Simulator AETNA

Oxidation Kinetics of Low-Sn Zircaloy-4 at the Temperature Range from 773 to 1,573K

A Theoretical Model of Annular Upward Flow in a Vertical Annulus Gap

Modeling for Evaluation of Debris Coolability in Lower Plenum of Reactor Pressure Vessel

Optimal Burnable Poison-Loading in a PWR with Carbon Coated Particle Fuel

Behavior of YSZ based Rock-Like Oxide Fuels under Simulated RIA Conditions

Influence of Dissolved Hydrogen on Oxide Film and PWSCC of Alloy 600 in PWR Primary Water

Application of General Purpose Fiber Optic Data Links to Radiation Measurements

Background-Cross-Section-Dependent Subgroup Parameters

Advanced PWR Core Calculation Based on Multi-group Nodal-transport Method in Three-dimensional Pin-by-Pin Geometry

Prediction of Critical Heat Flux in Annular Flow Using a Film Flow Model

The Crack Tip Solution Chemistry in Sensitized Stainless Steel in Simulated Boiling Water Reactor Water Studied Using a Microsampling Technique