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Volume 106

Number 2

Evaluation of a Severe Accident Management Strategy for Boiling Water Reactors—Drywell Flooding

Donghan Yu, Leiming Xing, William E. Kastenberg, David Okrent

Nuclear Technology / Volume 106 / Number 2 / May 1994 / Pages 139-154

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34971

Mean Importance Measures for Groups of Events in Fault Trees

F. Eric Haskin, Min Huang, M. Kent Sasser, Desmond W. Stack

Nuclear Technology / Volume 106 / Number 2 / May 1994 / Pages 155-167

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34972

Analysis of the Chemical Behavior of Iodine in the Suppression Tank of the LOFT Facility During Experiment LP-FP-2 with IODE and IMPAIR-2/M

Luis E. Herranz, Jesús Polo

Nuclear Technology / Volume 106 / Number 2 / May 1994 / Pages 168-176

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT94-A34973

Interaction of Nickel Ions with Magnetite Particles in High-Temperature Water

Kostadin A. Dinov, Kenkichi Ishigure, Daisuke Hiroishi, Chihiro Matsuura

Nuclear Technology / Volume 106 / Number 2 / May 1994 / Pages 177-185

Technical Paper / Material / dx.doi.org/10.13182/NT94-A34974

Modeling of Bubbly and Annular Two-Phase Flow in Subchannel Geometries with BACCHUS-3D/TP

Maurizio Bottoni, Robert W. Lyczkowski

Nuclear Technology / Volume 106 / Number 2 / May 1994 / Pages 186-201

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34975

Theoretical Modeling of Forced Convection Condensation of Steam in a Vertical Tube in the Presence of a Noncondensable Gas

Mansoor Siddique, Michael W. Golay, Mujid S. Kazimi

Nuclear Technology / Volume 106 / Number 2 / May 1994 / Pages 202-215

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34976

Optimal Reliable Control System Design for Steam Generators in Pressurized Water Reactors

Wencheng Wu, Chaung Lin

Nuclear Technology / Volume 106 / Number 2 / May 1994 / Pages 216-224

Technical Paper / Reactor Control / dx.doi.org/10.13182/NT94-A34977

Accelerating Learning of Neural Networks with Conjugate Gradients for Nuclear Power Plant Applications

Jaques Reifman, Javier E. Vitela

Nuclear Technology / Volume 106 / Number 2 / May 1994 / Pages 225-241

Technical Paper / Reactor Control / dx.doi.org/10.13182/NT94-A34978

Fuzzy Power Control Algorithm for a Pressurized Water Reactor

Yung-Joon Hah, Byong-Whi Lee

Nuclear Technology / Volume 106 / Number 2 / May 1994 / Pages 242-253

Technical Paper / Reactor Control / dx.doi.org/10.13182/NT94-A34979

Low-Power Experimental Study of the Demand Surface for Annular Geometry Fuel Elements with Upflow of Coolant

Allen C. Smith, James E. Blake, Michael T. Childerson, Ted R. Ohrn, Robert M. Privette

Nuclear Technology / Volume 106 / Number 2 / May 1994 / Pages 254-260

Technical Note / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT94-A34980

Film Dosimeters Based on Methylene Blue and Methyl Orange in Polyvinyl Alcohol

Woon Hyuk Chung, Arne Miller

Nuclear Technology / Volume 106 / Number 2 / May 1994 / Pages 261-264

Technical Note / Radiation Protection / dx.doi.org/10.13182/NT94-A34981