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Number 1

Table of Contents

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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT91-A16228

Number 2

Table of Contents
Instrumentation and Control Revamping (J.-L. Mourlevat, A. Parry, J.-F. Petretot, J.-F. Aschenbrenner)

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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT91-A34548

Number 3

Table of Contents

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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT91-A15819

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