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: 39(7)-39(12):2002.7-2002.12(P.705-1306)
• 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: 2002
• 出版年（W3CDTF）: 2002
• 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

Uncertainty Analyses in the Resolved Resonance Region of 235U, 238U, and 239Pu with the Reich-Moore R-Matrix Theory for JENDL-3.2

Nuclear Level Structure, B(E2)Gamma-transitions and Nucleon Interaction Data for 56Fe by a Unified Soft-rotator Model and Coupled-Channels Framework

Neutronic Optimization of Premoderator and Reflector for Decoupled Hydrogen Moderator in 1MW Spallation Neutron Source

Effect of Transplutonium Doping on Approach to Long-life Core in Uranium-fueled PWR

The Trigger Mechanism of Vapor Explosion

Low Corrosive Chemical Decontamination Method Using pH Control(2)Decomposition of Reducing Agent by Using Catalyst with Hydrogen Peroxide

Contribution to Understanding Iodine Sorption Mechanism onto Mixed Solid Alumina Cement and Calcium Compounds

Design of an Anti-Compton Spectrometer for Low-Level Radioactive Wastes using Monte Carlo Techniques

Conversion from Tooth Enamel Dose to Organ Doses for Electron Spin Resonance Dosimetry

Application and In-depth Assessment of RETRAN-3D for Best Estimate Analysis of Nuclear Power Plant Transients

Nonlinear Analytic and Semi-Analytic Nodal Methods for Multigroup Neutron Diffusion Calculations

A Linear Stability Analysis of a Vapor Film in Terms of the Triggering of Vapor Explosions

Fatigue Evaluation of Type 316 Stainless Steel Using Positron Annihilation Lineshape Analysis and β+-γ Coincidence Positron Lifetime Measurement

A Mechanism for Corrosion Rroduct Deposition on the Carbon Steel Piping in the Residual Heat Removal System of BWRs

Application of In-Service Temperature Lowering to Reduce Radioactivity Corrosion Product Deposition on Carbon Steel Piping of BWR Residual Heat Removal System

The Luminescence from a Long Lasting Phosphor Exposed to Alpha, Beta, and Gamma Rays

Effect of Radial Peaking Factor Limitation on Discharge Burnup

RETRAN Code Analysis of Tsuruga-2 Plant Chemical Volume Control System(CVCS) Reactor Coolant Leakage Incident

Raw Materials for Low-Activation Concrete Neutron Shields

Application of the Distributed Genetic Algorithm for In-Core Fuel Optimization Problems under Parallel Computational Environment

Measurement of Thermal Neutron Capture Cross Section and Resonance Integral of the 166mHo(n,γ)167Ho Reaction using a Two-Step Irradiation Technique

Transport Equivalent Diffusion Constants for Reflector Region in PWRs

Experiments and Analyses on Sodium Void Reactivity Worth in Uranium-Free Fast Reactor at FCA

Orientation Effects on Critical Heat Flux due to Flooding in Thin Rectangular Channel

Numerical Simulation of Aerosol Behavior in Turbulent Natural Convection

Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3

Tunneling in High-K Isomeric Decays

Development of General-Purpose Particle and Heavy Ion Transport Monte Carlo Code

Analytical Study on Detailed Void Distributions Inside BWR Fuel Bundle under Turbine Trip Event Considering Time-Dependent Pin Power Distributions

Modified Quasi-Steady-State Method to Evaluate the Mean Power Profiles of Nuclear Excursions in Fissile Solution