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

• 資料種別: 雑誌
• 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: 34(7)-34(12)=400-405:1997.7-1997.12
• 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: 1997
• 出版年（W3CDTF）: 1997
• 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
• ISSN（掲載誌）: 0022-3131
• ISSN-L（掲載誌）: 0022-3131
• 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
• 目録規則: 国立国会図書館逐次刊行物目録規則

目次

Numerical Study on Identification of Transfer Functions in a Feedback System and Model Reduction

Applicability of the ZND Detonation Model to Vapor Explosions

Characteristics of U3Si and U3Si2 Powders Prepared by Centrifugal Atomization

A Nuclear Magnetic Resonance Study on Ligand Exchange Reaction in U(VI)Nitrato Complex with n-Octyl(phenyl)-N,N-Diisobutylcarbamoylmethylphosphine Oxide in Acetone Containing Oxalic Acid

Small Gas Leakage Rate Measuring and Monitoring System for Spent Fuel Transport/Storage Cask

Effects of Spatial Harmonics on Thermal Neutron Spectra Measured by Time-of-Flight Method

New Sampling Method in Continuous Energy Monte Carlo Calculation for Pebble Bed Reactors

A New Estimation Method for Nuclide Number Densities in Equilibrium Cycle

Effect of Fast Neutron Irradiation on CdTe Radiation Detectors

Development of Intelligent Code System to Support Conceptual Design of Nuclear Reactor Core

Radiochemical Determination of Neutron Capture Cross Sections of 241Am

Development of a High Intensity RFQ at JAERI

Safety Analyses for Transient Behavior of Plasma and In-vessel Components during Plasma Abnormal Events in Fusion Reactor

Improvement of Fitting Method of Multiband Parameters for Cell Calculations

Nuclear Design Study on a Super High-burnup Fuel Assembly for Pressurized Water Reactors Using Transuranium

Role of Effective Distance in the Fission Mechanism Study by the Double-energy Measurement for Uranium Isotopes

Comparison between Equilibrium Cycle and Successive Multicycle Optimization Methods for In-Core Fuel Management of Pressurized Water Reactors

Inclusive Model-Based X-ray Detection Characteristics of Superconducting Tunnel Junctions

Thermochemical Prediction of Chemical Form Distributions of Fission Products in LWR Oxide Fuels Irradiated to High Burnup

Expanded Heat Treatment to Form Residual Compressive Hoop Stress on Inner Surface of Zirconium Alloy Tubing

Development of Dust Removal System Using Static Electricity for Fusion Experimental Reactors

Sensitivities of Some Characteristics of Nuclear Equilibrium State to One-Group Constants

Calculation of Coupling Coefficients of Coupled Reactors Theory Using the Generalized Perturbation Theory

A New Diagnosis Method Using Alarm Annunciation for Nuclear Power Plants

Recoupling and Decoupling of Parallel Loops in Simulated PIUS-type Reactor Shutdown and Restart Transients

Some Aspects of LWR′s Water Chemistry

Response of Large Nb-Based Tunnel Junction to X-Rays

Development of a Method for Evaluation of Pin-wise Power Distribution in Fuel Assemblies of Fast Reactors

Radiation Dosimeters for High Dose by Commercial PMOS Transistors Using Normalized Drain Current as Dosimetric Parameter

Influence of Scattered Neutrons on Void Fraction Measurement of Two-Phase Flow Using Thermal Neutron Radioscopy