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Home / Publications / Journals / Nuclear Technology / Volume 153 / Number 3

Volume 153

Number 3

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 / March 2006 / Pages 245-255

Technical Paper / Sodium Technology - Thermal Hydraulics / dx.doi.org/10.13182/NT06-2

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 / March 2006 / Pages 256-263

Technical Paper / Sodium Technology - Reactor Safety / dx.doi.org/10.13182/NT06-A3705

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 / March 2006 / Pages 264-273

Technical Paper / Sodium Technology - Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT06-A3706

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 / March 2006 / Pages 274-281

Technical Note / Sodium Technology - Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3707

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 / March 2006 / Pages 282-303

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT06-A3708

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 / March 2006 / Pages 304-314

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3709

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 / March 2006 / Pages 315-325

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3710

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 / March 2006 / Pages 326-340

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT06-A3711

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 / March 2006 / Pages 341-359

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT06-A3712

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 / March 2006 / Pages 360-364

Technical Note / Radiation Measurements and Instrumentation / dx.doi.org/10.13182/NT06-A3713

 

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