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Volume 102

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Nuclear Technology / Volume 102 / Number 3

June 1993

Table of Contents

Nuclear Technology / Volume 102 / Number 1

April 1993

Table of Contents

Nuclear Technology / Volume 102 / Number 2

May 1993

Development of Mixed-Oxide Fuel Manufacture in the United Kingdom and the Influence of Fuel Characteristics on Irradiation Performance

Hugh M. MacLeod, Geoffrey Yates

Nuclear Technology / Volume 102 / Number 1 / Pages 3-17

April 1993

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Plutonium Processing at the Siemens Hanau Fuel Fabrication Plant

Jürgen Krellmann

Nuclear Technology / Volume 102 / Number 1 / Pages 18-28

April 1993

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Price:$30.00

Irradiation Behavior of UO2/PuO2 Fuel in Light Water Reactors

Wolfgang Goll, Hans-Peter Fuchs, Reiner Manzel, Fritz U. Schlemmer

Nuclear Technology / Volume 102 / Number 1 / Pages 29-46

April 1993

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In-Pile Performance of Mixed-Oxide Fuel with Particular Emphasis on MIMAS Fuel

P. Deramaix, D. Haas, J. Van De Velde

Nuclear Technology / Volume 102 / Number 1 / Pages 47-53

April 1993

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Experience in PWR and BWR Mixed-Oxide Fuel Management

Gerhard J. Schlosser, Wolf-Dieter Krebs, Peter Urban

Nuclear Technology / Volume 102 / Number 1 / Pages 54-67

April 1993

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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

Format:

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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

Format:

Price:$30.00

Format:

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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

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

Format:

Price:$30.00
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