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Home / Publications / Journals / Nuclear Technology / Volume 94 / Number 3

Volume 94

Number 3

A Model of Crud Particle/Wall Interaction and Deposition in a Pressurized Water Reactor Primary System

Kostadin A. Dinov

Nuclear Technology / Volume 94 / Number 3 / June 1991 / Pages 281-285

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A15809

A Homogenization Technique for Strongly Heterogeneous Zones in Research Reactors

Jong Tai Lee, Byung Ho Lee, Nam Zin Cho, Se Kee Oh

Nuclear Technology / Volume 94 / Number 3 / June 1991 / Pages 286-296

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A15810

Analysis of Ex-Core Neutron Detector Response During a Loss-of-Coolant Accident

L. Michael Gundy, Anthony J. Baratta, George R. Imel,+, William A. Jester

Nuclear Technology / Volume 94 / Number 3 / June 1991 / Pages 297-312

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A15811

Results from the Power Burst Facility Severe Fuel Damage Test 1-4: A Simulated Severe Fuel Damage Accident with Irradiated Fuel Rods and Control Rods

David A. Petti, Zoel R. Martinson, Richard R. Hobbins, Daniel J. Osetek

Nuclear Technology / Volume 94 / Number 3 / June 1991 / Pages 313-335

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A15812

252Cf-Source-Driven Neutron Noise Measurements of Subcriticality for an Annular Tank Containing Aqueous Pu-U Nitrate

J. T. Mihalczo, E. D. Blakeman, G. E. Ragan, R. C. Kryter, H. Seino, R. C. Robinson

Nuclear Technology / Volume 94 / Number 3 / June 1991 / Pages 336-360

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A15813

The Iodine Spike Release Rate During a Steam Generator Tube Rupture

James P. Adams, Corwin L. Atwood

Nuclear Technology / Volume 94 / Number 3 / June 1991 / Pages 361-371

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT91-A15814

Thermal Stress Analyses of the Multilayered Fuel Particles of a Particle-Bed Reactor

Dean Dobranich, Mohamed S. El-Genk

Nuclear Technology / Volume 94 / Number 3 / June 1991 / Pages 372-382

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT91-A15815

Spent-Fuel Dry-Bath Oxidation Testing

Robert E. Einziger, Steven C. Marschman, H. Craig Buchanan

Nuclear Technology / Volume 94 / Number 3 / June 1991 / Pages 383-393

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT91-A15816

U-Tube Steam Generator Predictions: New Tube Bundle Convective Heat Transfer Correlations

Yassin A. Hassan, Mathangi Kalyanasundaram

Nuclear Technology / Volume 94 / Number 3 / June 1991 / Pages 394-406

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT91-A15817

Development of Statistical Core Thermal Design Methodology Using a Modified Latin Hypercube Sampling Method

Seung-Hyuk Lee, Hyun-Koon Kim, Sang-Ryeol Park, Soon-Heung Chang

Nuclear Technology / Volume 94 / Number 3 / June 1991 / Pages 407-415

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT91-A15818

Improvement in Fuel Utilization in Pressurized Heavy Water Reactors Due to Increased Heavy Water Purity

M. R. Balakrishnan

Nuclear Technology / Volume 94 / Number 3 / June 1991 / Pages 416-420

Technical Note / Economic / dx.doi.org/10.13182/NT91-A15819

 

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