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Home / Publications / Journals / Nuclear Technology / Volume 98 / Number 3

Volume 98

Number 3

The Reactor Physics Design of Gas-Cooled Cermet Reactors and Their Potential Application to Space Power Systems

S. N. Jahshan

Nuclear Technology / Volume 98 / Number 3 / June 1992 / Pages 257-276

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT92-A34658

Accident Management for a Loss of Feedwater in a Pressurized Water Reactor

Carmelo Billa, Francesco D’Auria, Giorgio Maria Galassi

Nuclear Technology / Volume 98 / Number 3 / June 1992 / Pages 277-288

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34659

An Analysis of Feed-and-Bleed Cooling of a Pressurized Water Reactor

Min Lee, Jiing-Huae Wu

Nuclear Technology / Volume 98 / Number 3 / June 1992 / Pages 289-306

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT92-A34660

A Prototype Expert System for the Monitoring of Defected Nuclear Fuel Elements in Canada Deuterium Uranium Reactors

Brent J. Lewis, Russell J. Green, Christopher W. T. Che

Nuclear Technology / Volume 98 / Number 3 / June 1992 / Pages 307-321

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT92-A34661

An Epithermal Neutron Beam for Neutron Capture Therapy at the Missouri University Research Reactor

Robert M. Brugger, Jing-Luen A. Shih, Hungyuan B. Liu

Nuclear Technology / Volume 98 / Number 3 / June 1992 / Pages 322-332

Technical Paper / Radiation Biology and Medicine / dx.doi.org/10.13182/NT92-A34662

Validation and Extension of a Correlation for Predicting Onset of Nucleate Boiling in Plate-Type Research Reactors

Efigenio Cubillos-Moreno, Mohamed Belhadj, Tunc Aldemir

Nuclear Technology / Volume 98 / Number 3 / June 1992 / Pages 333-348

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT92-A34663

Elementary Model to Predict the Pressure Loss Across a Spacer Grid Without a Mixing Vane

Nae-Hyun Kim, Sang Keun Lee, Kap Suk Moon

Nuclear Technology / Volume 98 / Number 3 / June 1992 / Pages 349-353

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT92-A34664

Bundle Critical Power Predictions Under Normal and Abnormal Conditions in Pressurized Water Reactors

Wen-Shan Lin, Bau-Shei Pei, Chien-Hsiung Lee

Nuclear Technology / Volume 98 / Number 3 / June 1992 / Pages 354-365

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT92-A34665

Application of Generation and Condensation Models to Predict Subcooled Boiling Void at Low Pressures

VIjay Chatoorgoon, Geoffrey R. Dimmick, Michael B. Carver, William N. Selander, Mamdouh Shoukri

Nuclear Technology / Volume 98 / Number 3 / June 1992 / Pages 366-378

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT92-A34666

Measurements of Gamma-Ray Shielding Properties of Ilmenite-Magnetite Concrete and Polyboron Slabs Using a 252Cf Source

F. U. Ahmed, S. I. Bhuiyan, A. S. Mollah, M. M. Rahman

Nuclear Technology / Volume 98 / Number 3 / June 1992 / Pages 379-386

Technical Note / Radiation Protection / dx.doi.org/10.13182/NT92-A34667

 

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