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Volume 102

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Investigation of the Nuclear Inventories of High-Exposure PWR Mixed-Oxide Fuels with Multiple Recycling of Self-Generated Plutonium

Hans-Werner Wiese

Nuclear Technology / Volume 102 / Number 1 / Pages 68-80

April 1993

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Validation of Fuel Bundle Mechanical Performance Code ÉTOILE with Bundle/Duct Interaction Experimental Data

Masatoshi Nakagawa

Nuclear Technology / Volume 102 / Number 1 / Pages 81-89

April 1993

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Development of a Connectivity Verification System for Sequence Diagrams of Power Plants

Mitsuko Fukuda, Naoyuki Yamada, Ken’ichi Kan, Mitsugu Utsunomiya

Nuclear Technology / Volume 102 / Number 1 / Pages 90-99

April 1993

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Global Analysis of Bundle Behavior in Pressurized Water Reactor Specific CORA Experiments

Wolfgang Hering, Kazuo Minato, Fumihisa Nagase

Nuclear Technology / Volume 102 / Number 1 / Pages 100-115

April 1993

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RELAP5/MOD2 Split Reactor Vessel Model and Steamline Break Analysis

Stojan Petelin, Borut Mavko, Oton Gortnar

Nuclear Technology / Volume 102 / Number 1 / Pages 116-124

April 1993

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Ex-Core Detector Response Caused by Control Rod Misalignment Observed During Operation of the Reactor on the Nuclear Ship Mutsu

Masafumi Itagaki, Yoshinori Miyoshi, Kazuhiko Gakuhari, Noboru Okada, Tomohiro Sakai

Nuclear Technology / Volume 102 / Number 1 / Pages 125-136

April 1993

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Price:$30.00

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Comments on “Failure Probability of Axially Cracked Steam Generator Tubes: A Probabilistic Fracture Mechanics Model”

J. Hopenfeld

Nuclear Technology / Volume 102 / Number 1 / Page 143

April 1993

Response to “Comments on ‘Failure Probability of Axially Cracked Steam Generator Tubes: A Probabilistic Fracture Mechanics Model’”

B. Mavko, L. Cizelj

Nuclear Technology / Volume 102 / Number 1 / Pages 143-144

April 1993

Table of Contents

Nuclear Technology / Volume 102 / Number 2

May 1993

Transient and Load-Following Characteristics of a Fully Integrated Single-Cell Thermionic Fuel Element

Mohamed S. El-Genk, Huimin Xue, Chris Murray

Nuclear Technology / Volume 102 / Number 2 / Pages 145-166

May 1993

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Proof of Principle of a Nuclear Turbine Flowmeter

Tim H. J. J. Van Der Hagen

Nuclear Technology / Volume 102 / Number 2 / Pages 167-176

May 1993

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Application of Neural Networks to a Connectionist Expert System for Transient Identification in Nuclear Power Plants

Se Woo Cheon, Soon Heung Chang

Nuclear Technology / Volume 102 / Number 2 / Pages 177-191

May 1993

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Reduction of the Reactivity of Water Ingress in Modular Pebble-Bed High-Temperature Reactors

E. Teuchert, K. A. Haas, H. J. Rütten, Yuliang Sun

Nuclear Technology / Volume 102 / Number 2 / Pages 192-195

May 1993

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Error Propagation for Gamma Spectroscopy and Neutron Coincidence Counting for Plutonium-Bearing Materials

Ming-Shih Lu, Theodor Teichmann

Nuclear Technology / Volume 102 / Number 2 / Pages 196-209

May 1993

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Evaluation of Fission Gas Release in High-Burnup Light Water Reactor Fuel Rods

John O. Barner, Mitchel E. Cunningham, Maxwell D. Freshley, Donald D. Lanning

Nuclear Technology / Volume 102 / Number 2 / Pages 210-231

May 1993

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The Effect of Correlated Flow in Pulsed Column Contactors Using the Purex Process

John F. Geldard, Adolph L. Beyerlein

Nuclear Technology / Volume 102 / Number 2 / Pages 252-258

May 1993

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Characterization of the Thermalness of a Fissile System with a Two-Group Diffusion Theory Parameter

Brent B. Bredehoft, Robert D. Busch

Nuclear Technology / Volume 102 / Number 2 / Pages 259-269

May 1993

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LRAD-Based Alpha-Particle Contamination Monitoring of Personnel and Equipment

Duncan W. MacArthur, Krag S. Allander, John A. Bounds, J. Lee McAtee

Nuclear Technology / Volume 102 / Number 2 / Pages 270-276

May 1993

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