Journal of Nuclear Science and Technology, Volume 39, Issue 5 (2002)

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Journal of Nuclear Science and Technology, Volume 39, Issue 5 (2002)

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Original Articles

Article
Calculation of Gamma-Ray Buildup Factors up to Depths of 100 mfp by the Method of Invariant Embedding, (I)
Analysis of Accuracy and Comparison with Other Data
Akinao SHIMIZU
Pages: 477-486
Published online: 07 Feb 2012
AbstractforCalculation of Gamma-Ray Buildup Factors up to Depths of 100 mfp by the Method of Invariant Embedding, (I) | References | PDF (153.3 KB)
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Article
Effect of Moderator Density Distribution of Annular Flow on Fuel Assembly Neutronic Characteristics in Boiling Water Reactor Cores
Tsuyoshi AMA, Hideaki IKEDA, Shinya KOSAKA, Hideaki HYOUDOU & Toshikazu TAKEDA
Pages: 487-498
Published online: 07 Feb 2012
AbstractforEffect of Moderator Density Distribution of Annular Flow on Fuel Assembly Neutronic Characteristics in Boiling Water Reactor Cores | References | PDF (320.7 KB)
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Article
Determination of Gamma-Ray Exposure Rate from Short-Lived Fission Products under Criticality Accident Conditions
Hiroshi YANAGISAWA, Akio OHNO & Eijyu AIZAWA
Pages: 499-505
Published online: 07 Feb 2012
AbstractforDetermination of Gamma-Ray Exposure Rate from Short-Lived Fission Products under Criticality Accident Conditions | References | PDF (294.5 KB)
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Article
Concept of Erbium Doped Uranium Oxide Fuel Cycle in Light Water Reactors
Vladimir BARCHEVTSEV, Vladimir ARTISYUK & Hisashi NINOKATA
Pages: 506-513
Published online: 07 Feb 2012
AbstractforConcept of Erbium Doped Uranium Oxide Fuel Cycle in Light Water Reactors | References | PDF (139.4 KB)
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Article
Detection Method of Fatigue Damage in Carbon Steel Using Laser Ultrasonics
Takao TANAKA & Yasukazu IZAWA
Pages: 514-519
Published online: 07 Feb 2012
AbstractforDetection Method of Fatigue Damage in Carbon Steel Using Laser Ultrasonics | References | PDF (243.1 KB)
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Article
Verification for Flow Analysis Capability in the Model of Three-Dimensional Natural Convection with Simultaneous Spreading, Melting and Solidification for the Debris Coolability Analysis Module in the Severe Accident Analysis Code ‘SAMPSON’, (II)
Masataka HIDAKA, Nobuhide SATO & Hiroshi UJITA
Pages: 520-530
Published online: 07 Feb 2012
AbstractforVerification for Flow Analysis Capability in the Model of Three-Dimensional Natural Convection with Simultaneous Spreading, Melting and Solidification for the Debris Coolability Analysis Module in the Severe Accident Analysis Code ‘SAMPSON’, (II) | References | PDF (429.4 KB)
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Article
Intergranular Stress Corrosion Cracking of Type 304 Stainless Steels Treated with Inhibitive Chemicals in Simulated Boiling Water Reactor Environments
Tsung-Kuang YEH, Ming-Yong LEE & Chuen-Horng TSAI
Pages: 531-539
Published online: 07 Feb 2012
AbstractforIntergranular Stress Corrosion Cracking of Type 304 Stainless Steels Treated with Inhibitive Chemicals in Simulated Boiling Water Reactor Environments | References | PDF (213 KB)
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Article
Silicate Anion Structural Change in Calcium Silicate Hydrate Gel on Dissolution of Hydrated Cement
Kazuko HAGA, Masahito SHIBATA, Michihiko HIRONAGA, Satoru TANAKA & Shinya NAGASAKI
Pages: 540-547
Published online: 07 Feb 2012
AbstractforSilicate Anion Structural Change in Calcium Silicate Hydrate Gel on Dissolution of Hydrated Cement | References | PDF (114.4 KB)
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TECHNICAL REPORT

Article
Resonance Self-Shielding Corrections for Activation Cross Section Measurements
Oleg SHCHERBAKOV & Hideo HARADA
Pages: 548-553
Published online: 07 Feb 2012
AbstractforResonance Self-Shielding Corrections for Activation Cross Section Measurements | References | PDF (147.4 KB)
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Article
A Transient Modal Analysis of a BWR Instability Event
Damián GINESTAR, Rafael MIRÓ, Gumersindo VERDÚ & Dieter HENNIG
Pages: 554-563
Published online: 07 Feb 2012
AbstractforA Transient Modal Analysis of a BWR Instability Event | References | PDF (283.2 KB)
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Article
Application of an Artificial Neural Network in Reactor Thermohydraulic Problem: Prediction of Critical Heat Flux
Guanghui SU, Kenji FUKUDA, Dounan JIA & Koji MORITA
Pages: 564-571
Published online: 07 Feb 2012
AbstractforApplication of an Artificial Neural Network in Reactor Thermohydraulic Problem: Prediction of Critical Heat Flux | References | PDF (241.3 KB)
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Article
Analysis of Flows around a BWR Spacer by the Two-Fluid Particle Interaction Method
Noriyuki SHIRAKAWA, Yuichi YAMAMOTO, Hideki HORIE & Shigeaki TSUNOYAMA
Pages: 572-581
Published online: 07 Feb 2012
AbstractforAnalysis of Flows around a BWR Spacer by the Two-Fluid Particle Interaction Method | References | PDF (323.6 KB)
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SHORT NOTE

Article
Numerical Analysis of Uranium Solubility in Compacted Bentonite by Applying the Activity Correction for Strong Interaction between Liquid/Solid Interface
Toshiaki OHE, Chiharu KAWADA & Eri SANO
Pages: 582-585
Published online: 07 Feb 2012
First Page PreviewforNumerical Analysis of Uranium Solubility in Compacted Bentonite by Applying the Activity Correction for Strong Interaction between Liquid/Solid Interface | References | PDF (51.5 KB)
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