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Home / Publications / Journals / Nuclear Technology / Volume 102 / Number 2

Volume 102

Number 2

Transient and Load-Following Characteristics of a Fully Integrated Single-Cell Thermionic Fuel Element

Mohamed S. El-Genk, Huimin Xue, Chris Murray

Nuclear Technology / Volume 102 / Number 2 / May 1993 / Pages 145-166

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT93-A34813

Proof of Principle of a Nuclear Turbine Flowmeter

Tim H. J. J. Van Der Hagen

Nuclear Technology / Volume 102 / Number 2 / May 1993 / Pages 167-176

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT93-A34814

Application of Neural Networks to a Connectionist Expert System for Transient Identification in Nuclear Power Plants

Se Woo Cheon, Soon Heung Chang

Nuclear Technology / Volume 102 / Number 2 / May 1993 / Pages 177-191

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34815

Reduction of the Reactivity of Water Ingress in Modular Pebble-Bed High-Temperature Reactors

E. Teuchert, K. A. Haas, H. J. Rütten, Yuliang Sun

Nuclear Technology / Volume 102 / Number 2 / May 1993 / Pages 192-195

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT93-A34816

Error Propagation for Gamma Spectroscopy and Neutron Coincidence Counting for Plutonium-Bearing Materials

Ming-Shih Lu, Theodor Teichmann

Nuclear Technology / Volume 102 / Number 2 / May 1993 / Pages 196-209

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT93-A34817

Evaluation of Fission Gas Release in High-Burnup Light Water Reactor Fuel Rods

John O. Barner, Mitchel E. Cunningham, Maxwell D. Freshley, Donald D. Lanning

Nuclear Technology / Volume 102 / Number 2 / May 1993 / Pages 210-231

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT93-A34818

Development of the FACE Computer Code to Evaluate the Safety of an Air Ventilation System During a Postulated Solvent Fire in a Nuclear Fuel Reprocessing Plant

Gunji Nishio, Noboru Yamazaki

Nuclear Technology / Volume 102 / Number 2 / May 1993 / Pages 232-251

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT93-A34819

The Effect of Correlated Flow in Pulsed Column Contactors Using the Purex Process

John F. Geldard, Adolph L. Beyerlein

Nuclear Technology / Volume 102 / Number 2 / May 1993 / Pages 252-258

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT93-A34820

Characterization of the Thermalness of a Fissile System with a Two-Group Diffusion Theory Parameter

Brent B. Bredehoft, Robert D. Busch

Nuclear Technology / Volume 102 / Number 2 / May 1993 / Pages 259-269

Technical Paper / Nuclear Criticality Safety / dx.doi.org/10.13182/NT93-A34821

LRAD-Based Alpha-Particle Contamination Monitoring of Personnel and Equipment

Duncan W. MacArthur, Krag S. Allander, John A. Bounds, J. Lee McAtee

Nuclear Technology / Volume 102 / Number 2 / May 1993 / Pages 270-276

Technical Paper / Radiation Protection / dx.doi.org/10.13182/NT93-A34822

Automatic Reactor Power Control for a Pressurized Water Reactor

Jung-In Choi, Yung-Joon Hah, Un-Chul Lee

Nuclear Technology / Volume 102 / Number 2 / May 1993 / Pages 277-286

Technical Paper / Reactor Operation / dx.doi.org/10.13182/NT93-A34823

 

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