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Volume 153

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Simulant Melt Experiments on Thermal and Metallurgical Performance of the In-Vessel Core Catcher

Kyoung-Ho Kang, Rae-Joon Park, Sang-Baik Kim, K.Y. Suh, F. B. Cheung, J. L. Rempe

Nuclear Technology / Volume 153 / Number 2 / Pages 208-223

February 2006

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Breeding of 242mAm in a Fast Reactor

Y. Ronen, M. Aboudy, D. Regev

Nuclear Technology / Volume 153 / Number 2 / Pages 224-233

February 2006

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The Temperature Feature on the Step-Up Process of the Hydraulic Control Rod Driving System

Yanhua Zheng, Hanliang Bo, Duo Dong

Nuclear Technology / Volume 153 / Number 2 / Pages 234-239

February 2006

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Introduction

Nicholas Tsoulfanidis

Nuclear Technology / Volume 153 / Number 3 / Page 243

March 2006

The Development of SIMMER-III, An Advanced Computer Program for LMFR Safety Analysis, and Its Application to Sodium Experiments

Y. Tobita, Sa. Kondo, H. Yamano, K. Morita, W. Maschek, P. Coste, T. Cadiou

Nuclear Technology / Volume 153 / Number 3 / Pages 245-255

March 2006

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Evaluation of the Accident Scenario Initiated by a Total Instantaneous Blockage in a Phénix Subassembly

Thierry Cadiou, Jacky Louvet

Nuclear Technology / Volume 153 / Number 3 / Pages 256-263

March 2006

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Contribution of Phénix to the Development of Transmutation Fuels and Targets in Sodium Fast Breeder Reactors

S. Pillon, F. Sudreau, G. Gaillard-Groléas

Nuclear Technology / Volume 153 / Number 3 / Pages 264-273

March 2006

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Phénix Steam Generator Module Repair: Sodium Removal Process, Ultrasonic Controls, and Repair Method

Ch. Cavagna, O. Gastaldi, L. Martin, V. Grabon

Nuclear Technology / Volume 153 / Number 3 / Pages 274-281

March 2006

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Study of Solid Moderators for the Thermal-Spectrum Supercritical Water-Cooled Reactor

Jacopo Buongiorno, James W. Sterbentz, Philip E. MacDonald

Nuclear Technology / Volume 153 / Number 3 / Pages 282-303

March 2006

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Root Cause of Instability in Liquid Zone Control System of CANDU Reactor

Sang-Nyung Kim, Byung-Marn Koh, Joon-Suk Ji

Nuclear Technology / Volume 153 / Number 3 / Pages 304-314

March 2006

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Consequences of Different Types of Contact Between Water and Molten Steel: The ANAIS Experiments

Michel Amblard, Jean-Marc Delhaye, Karine Froment, Jean-Marie Seiler, Bruno Tourniaire

Nuclear Technology / Volume 153 / Number 3 / Pages 315-325

March 2006

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Robust Dynamic Sensor Fault Detection and Isolation of Helical Coil Steam Generator Systems Using a Subspace Identification Technique

Ke Zhao, Belle R. Upadhyaya, Richard T. Wood

Nuclear Technology / Volume 153 / Number 3 / Pages 326-340

March 2006

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Phenomenology of Baneberry Nuclear Event Revisited with 3-D Finite Element Transient Simulation

Rajeev Ranjan, R. K. Singh, S. K. Sikka, Anil Kakodkar

Nuclear Technology / Volume 153 / Number 3 / Pages 341-359

March 2006

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Evaluation of the Efficiency of Gamma Spectrometers for Analyzing Environmental Samples with Unknown Elemental Composition

Nader M. A. Mohamed, M. Abou Mandour, M. K. Shaat, Alya A. Badawi

Nuclear Technology / Volume 153 / Number 3 / Pages 360-364

March 2006

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