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Volume 109

Number 2

Modeling of Molten Metal/Water Interactions

Ali Uludogan, Michael L. Corradini

Nuclear Technology / Volume 109 / Number 2 / February 1995 / Pages 171-186

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT109-171

Influence of Isolation Condensers on Boiling Water Reactor Performance During an Anticipated Transient Without Scram

Hasna J. Khan, Hsiang-Shou Cheng, Upendra S. Rohatgi

Nuclear Technology / Volume 109 / Number 2 / February 1995 / Pages 187-206

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A35052

Iodine Release During a Steam Generator Tube Rupture

James P. Adams

Nuclear Technology / Volume 109 / Number 2 / February 1995 / Pages 207-215

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A35053

Extraction Chromatographic Separation of Minor Actinides from PUREX High-Level Wastes Using CMPO

J. N. Mathur, M. S. Murali, R. H. Iyer, A. Ramanujam, P. S. Dhami, V. Gopalakrishnan, M. K. Rao, L. P. Badheka, Asoke Banerji

Nuclear Technology / Volume 109 / Number 2 / February 1995 / Pages 216-225

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT95-A35054

Reactor-Based Prompt Gamma Neutron Activation Setup Using a Low-Power Research Reactor

Chien Chung, Liq-Ji Yuan

Nuclear Technology / Volume 109 / Number 2 / February 1995 / Pages 226-235

Technical Paper / Radiation Application / dx.doi.org/10.13182/NT95-A35055

Experimental Study on Flow Rate Measurement of Buoyancy-Driven Exchange Flow

Motoo Fumizawa

Nuclear Technology / Volume 109 / Number 2 / February 1995 / Pages 236-245

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35056

Fundamental Study on Duplex Steam Generator Tubes for Liquid-Metal-Cooled Fast Reactors

Masanori Aritomi, Tomoaki Mizushima, Hiroshi Yabuta

Nuclear Technology / Volume 109 / Number 2 / February 1995 / Pages 246-254

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35057

Intelligent Alarm-Processing System for Nuclear Power Plants

Norio Naito, Shiroh Ohtsuka

Nuclear Technology / Volume 109 / Number 2 / February 1995 / Pages 255-264

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT95-A35058

In Situ Gamma Spectrometry of Piping in a CANDU Heat Transport System — Application During Decontamination

Aamir Husain, Calvin E. Breckenridge, David Storey

Nuclear Technology / Volume 109 / Number 2 / February 1995 / Pages 265-274

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT95-A35059

Simulation of a Marine Nuclear Reactor

Tsuyoshi Kusunoki, Masahiko Kyouya, Hideo Kobayashi, Masa-Aki Ochiai

Nuclear Technology / Volume 109 / Number 2 / February 1995 / Pages 275-285

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT95-A35060

Artificial Neural Networks Versus Conventional Methods for Boiling Water Reactor Stability Monitoring

Tim H. J. J. van der Hagen

Nuclear Technology / Volume 109 / Number 2 / February 1995 / Pages 286-305

Technical Paper / Reactor Control / dx.doi.org/10.13182/NT95-A35061