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Home / Publications / Journals / Nuclear Technology / Volume 94

Volume 94

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Number 1

Measurements of Hideout Phenomena in Tube-Support-Plate Crevices

R. C. Wang, Chin Pan, Chuen-Horng Tsai

Nuclear Technology / Volume 94 / Number 1 / April 1991 / Pages 1-14

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A16217

Validation of Light Water Reactor Calculation Methods and JEF-1—Based Data Libraries by TRX and BAPL Critical Experiments

Sandro Pelloni, Peter Grimm, D. R. Mathews, J. M. Paratte

Nuclear Technology / Volume 94 / Number 1 / April 1991 / Pages 15-27

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT91-A16218

Comparison of Three-Dimensional Fine and Coarse Nodalization of the Reactor Vessel for a Small-Break Loss-of-Coolant Accident

Bahram Nassersharif, James S. Peery, Evelyn M. Mullen, Stephen R. Behling

Nuclear Technology / Volume 94 / Number 1 / April 1991 / Pages 28-43

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A16219

COTTAP: A Computer Code for Simulation of Thermal Transients in Secondary Containments of Boiling Water Reactors

Mark A. Chaiko, Michael J. Murphy

Nuclear Technology / Volume 94 / Number 1 / April 1991 / Pages 44-55

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A16220

Chemical Behavior of Fission Products in Core Heatup Accidents in High-Temperature Gas-Cooled Reactors

Rainer Moormann, Klaus Hilpert

Nuclear Technology / Volume 94 / Number 1 / April 1991 / Pages 56-67

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A16221

An Optimization Study for the Reactor Vessel Auxiliary Cooling System of a Pool Liquid-Metal Reactor

Constantine P. Tzanos, Jack H. Tessier, Dean R. Pedersen

Nuclear Technology / Volume 94 / Number 1 / April 1991 / Pages 68-79

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A16222

Measurements of Iodine Uptake in Falling Water Droplets

M. Lee Hyder

Nuclear Technology / Volume 94 / Number 1 / April 1991 / Pages 80-86

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A16223

Plutonium Reload Experience in French Pressurized Water Reactors

Michel Rome, Massimo Salvatores, Jacques Mondot, Michel Le Bars

Nuclear Technology / Volume 94 / Number 1 / April 1991 / Pages 87-98

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT91-A16224

The Interaction of Iodine with Insoluble Residue in the Dissolution of Simulated Spent-Fuel Pellets

Tsutomu Sakurai, Akira Takahashi, Niroh Ishikawa, Yoshihide Komaki

Nuclear Technology / Volume 94 / Number 1 / April 1991 / Pages 99-107

Technical Paper / Enrichment and Reprocessing / dx.doi.org/10.13182/NT91-A16225

Generation and Decomposition Behavior of Nitrous Acid During Dissolution of UO2 Pellets by Nitric Acid

Tetsuo Fukasawa, Yoshihiro Ozawa, Fumio Kawamura

Nuclear Technology / Volume 94 / Number 1 / April 1991 / Pages 108-113

Technical Paper / Enrichment and Reprocessing / dx.doi.org/10.13182/NT91-A16226

Corrosion Cells: An Important Factor in Localized Waste Package Geochemistry?

John C. Walton

Nuclear Technology / Volume 94 / Number 1 / April 1991 / Pages 114-123

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT91-A16227

Two Simplified Methods to Determine Void Fractions for Two-Phase Flow

Yin-Pang Ma, Nien-Mien Chung, Bau-Shei Pei, Wei-Keng Lin, Yih-Yun Hsu

Nuclear Technology / Volume 94 / Number 1 / April 1991 / Pages 124-133

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT91-A16228

Number 2

ADREA-I: A Three-Dimensional Transient Transport Code for Complex Terrain and Other Applications

John G. Bartzis, Alexander G. Venetsanos, Melpomeni Varvayanni, Nicolas Catsaros, Afroditi Megaritou

Nuclear Technology / Volume 94 / Number 2 / May 1991 / Pages 135-148

Technical Paper / Advances in Reactor Accident Consequence Assessment / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34537

Real-Time Systems for the Assessment of the Radiological Impact of Radionuclides Released into the Atmosphere

P. Jacob, W. Jacobi, H. Müller, H.G. Paretzke, G. Pröhl, J. Eklund, J. Gregor, R. Stapel

Nuclear Technology / Volume 94 / Number 2 / May 1991 / Pages 149-160

Technical Paper / Advances in Reactor Accident Consequence Assessment / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34538

The CEC Research Program on Methods for Assessing the Radiological Impact of Accidents (MARIA)

G. Neale Kelly, Martial Olast, Jaak Sinnaeve

Nuclear Technology / Volume 94 / Number 2 / May 1991 / Pages 161-176

Technical Paper / Advances in Reactor Accident Consequence Assessment / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34539

Structure, Important Features, and Illustrative Results of the New UFOMOD Program System in Assessing the Radiological Consequences of Nuclear Accidents

Joachim Ehrhardt, Klaus Burkart, Friedmar Fischer, Irmgard Hasemann, Hans-Jürgen Panitz, Claudia Steinhauer

Nuclear Technology / Volume 94 / Number 2 / May 1991 / Pages 177-195

Technical Paper / Advances in Reactor Accident Consequence Assessment / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34540

An Outline of COSYMA, A New Program Package for Accident Consequence Assessments

Joachim Ehrhardt, J. A. Jones

Nuclear Technology / Volume 94 / Number 2 / May 1991 / Pages 196-203

Technical Paper / Advances in Reactor Accident Consequence Assessment / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34541

Radiological Health Effects Models for Nuclear Power Plant Accident Consequence Analysis — An Update (1990)

John S. Evans

Nuclear Technology / Volume 94 / Number 2 / May 1991 / Pages 204-212

Technical Paper / Advances in Reactor Accident Consequence Assessment / Radiation Biology and Environment / dx.doi.org/10.13182/NT91-A34542

An Analytical Solution for the Calculation of the Transient Transport of Gaseous Species in Nuclear Fuel Pore Channels

Constantinos Syros,* Claudio Ronchi, Cinzia Spanó

Nuclear Technology / Volume 94 / Number 2 / May 1991 / Pages 213-227

Technical Paper / Advances in Reactor Accident Consequence Assessment / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34543

A Simple Fuzzy Simulation Model for Nuclear Reactor System Dynamics

Hiroshi Matsuoka

Nuclear Technology / Volume 94 / Number 2 / May 1991 / Pages 228-241

Technical Paper / Advances in Reactor Accident Consequence Assessment / Nuclear Reactor Safety / dx.doi.org/10.13182/NT91-A34544

The Effect of Weathering on Charcoal Filter Performance: I. The Adsorption and Desorption Behavior of Contaminants

Jungsook Clara Wren, Chris J. Moore

Nuclear Technology / Volume 94 / Number 2 / May 1991 / Pages 242-251

Technical Paper / Advances in Reactor Accident Consequence Assessment / Material / dx.doi.org/10.13182/NT91-A34545

The Effect of Weathering on Charcoal Filter Performance: II. The Effect of Contaminants On The CH3I Removal Efficiency of Teda Charcoal

Jungsook Clara Wren, Chris J. Moore

Nuclear Technology / Volume 94 / Number 2 / May 1991 / Pages 252-261

Technical Paper / Advances in Reactor Accident Consequence Assessment / Material / dx.doi.org/10.13182/NT91-A34546

A Digital Data Acquisition Approach for Research Reactors

Edward P. Ficaro, David K. Wehe

Nuclear Technology / Volume 94 / Number 2 / May 1991 / Pages 262-269

Technical Paper / Advances in Reactor Accident Consequence Assessment / Reactor Operation / dx.doi.org/10.13182/NT91-A34547

Power Prediction in Nuclear Power Plants Using a Back-Propagation Learning Neural Network

Myung-Sub Roh, Se-Woo Cheon, Soon-Heung Chang

Nuclear Technology / Volume 94 / Number 2 / May 1991 / Pages 270-278

Technical Paper / Advances in Reactor Accident Consequence Assessment / Reactor Operation / dx.doi.org/10.13182/NT91-A34548

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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