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Home / Publications / Journals / Nuclear Technology / Volume 96 / Number 3

Volume 96

Number 3

Study of Coolant Activation and Dose Rates with Flow Rate and Power Perturbations in Pool-Type Research Reactors

Nasir M. Mirza, Sikander M. Mirza, N. Ahmad

Nuclear Technology / Volume 96 / Number 3 / December 1991 / Pages 237-247

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A34586

Evaluation of a Dilute Chemical Decontaminant for Pressurized Heavy Water Reactors

S. Velmurugan, S. V. Narasimhan, P. K. Mathur, K. S. Venkateswarlu

Nuclear Technology / Volume 96 / Number 3 / December 1991 / Pages 248-258

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT96-248

Estimates of Rupture Probabilities for Nuclear Power Plant Components: Expert Judgment Elicitation

Truong V. Vo, Patrick G. Heasler, Steven R. Doctor, Frederic A. Simonen, Bryan F. Gore

Nuclear Technology / Volume 96 / Number 3 / December 1991 / Pages 259-271

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34588

The Response of Ex-Core Neutron Detectors to Large- and Small-Break Loss-of-Coolant Accidents in Pressurized Water Reactors

E. Wilson Okyere, Anthony J. Baratta, William A. Jester

Nuclear Technology / Volume 96 / Number 3 / December 1991 / Pages 272-289

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34589

Temporary Core Liquid Level Depression During a Cold-Leg Small-Break Loss-of-Coolant Accident: The Effect of Break Size and Power Level

Yasuo Koizumi, Hiroshige Kumamaru, Yuichi Mimura+, Yutaka Kukita, Kanji Tasaka†

Nuclear Technology / Volume 96 / Number 3 / December 1991 / Pages 290-301

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34590

Quantitative Fuel Motion Determination with the CABRI Fast Neutron Hodoscope: Evaluation Methods and Results

Kurt Baumung, Gérard Augier

Nuclear Technology / Volume 96 / Number 3 / December 1991 / Pages 302-313

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT91-A34591

A Model to Predict the Ultimate Failure of Coated Fuel Particles During Core Heatup Events

Toru Ogawa, Kazuo Minato, Kousaku Fukuda, Masami Numata, Hideshi Miyanishi, Hajime Sekino, Hideo Matsushima, Tadaharu Itoh, Shigeo Kado, Ishio Takahashi

Nuclear Technology / Volume 96 / Number 3 / December 1991 / Pages 314-322

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT91-A34592

High-Temperature Reactor Fuel Fission Product Release and Distribution at 1600 to 1800°C

Werner Schenk, Heinz Nabielek

Nuclear Technology / Volume 96 / Number 3 / December 1991 / Pages 323-336

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT96-3-323

Isotope Separation by Chemical Exchange: A Computer Simulation

Heinrich R. Obermoller, David A. White

Nuclear Technology / Volume 96 / Number 3 / December 1991 / Pages 337-345

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT91-A34594

Neutron Effects on Borated Stainless Steel

S. E. Soliman, D. L. Youchison, A. J. Baratta, T. A. Balliett

Nuclear Technology / Volume 96 / Number 3 / December 1991 / Pages 346-352

Technical Paper / Material / dx.doi.org/10.13182/NT91-A34595

Operating Margin of Soviet RBMK-1000 Nuclear Power Reactors

James M. Adams, Lawrence E. Hochreiter, Gordon E. Robinson

Nuclear Technology / Volume 96 / Number 3 / December 1991 / Pages 353-360

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT91-A34596

 

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