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Number 1

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Investigation of Failed Fuel Detection and Location Using a Flux Tilting Method in a Fast Breeder Reactor
Masao Hamada, Kunio Uehara, Kazuyoshi Muramatsu, Takanobu Kamei, Tetsuo Tamaoki, Mitsuaki Yamaoka, † Yukio Sonoda, Yuji Sano, Masuo Sato, Takayuki Sudo
Nuclear Technology | Volume 98 | Number 1 | April 1992 | Pages 1-13
Technical Paper | Fast Reactor Safety / Fission Reactor | doi.org/10.13182/NT92-A34646
Study of Thermal-Hydraulic Characteristics During Decay Heat Removal in a Pool-Type Fast Breeder Reactor
Masayoshi Akutsu, Yoshinobu Okabe, Kazuziro Satoh, Hideki Kamide, Kenji Hayashi, Nobuyuki Naohara, Kengo Iwashige, Yoji Shibata
Nuclear Technology | Volume 98 | Number 1 | April 1992 | Pages 14-26
Technical Paper | Fast Reactor Safety / Fission Reactor | doi.org/10.13182/NT92-A34647
Investigations of Sloshing Fluid Motions in Pools Related to Recriticalities in Liquid-Metal Fast Breeder Reactor Core Meltdown Accidents
Werner Maschek, Claus Dieter Munz, Leonhard Meyer
Nuclear Technology | Volume 98 | Number 1 | April 1992 | Pages 27-43
Technical Paper | Fast Reactor Safety / Nuclear Reactor Safety | doi.org/10.13182/NT92-A34648
Modeling Transient Fission Gas Behavior for Solid, Melting, and Molten Fuel in the Computer Program LAKU
L. Väth
Nuclear Technology | Volume 98 | Number 1 | April 1992 | Pages 44-53
Technical Paper | Fast Reactor Safety / Nuclear Reactor Safety | doi.org/10.13182/NT92-A34649
Improvement of Evaluation Method for Initiating-Phase Energetics Based on CABRI-1 In-Pile Experiments
Nobuyuki Nonaka, Ikken Sato
Nuclear Technology | Volume 98 | Number 1 | April 1992 | Pages 54-69
Technical Paper | Fast Reactor Safety / Nuclear Reactor Safety | doi.org/10.13182/NT92-A34650
Molten Fuel Propagation in Sodium-Filled Fast Reactor Subassembly Geometries
Allen J. Edwards, M. J. Bird, Michael K. Denham
Nuclear Technology | Volume 98 | Number 1 | April 1992 | Pages 70-78
Technical Paper | Fast Reactor Safety / Nuclear Reactor Safety | doi.org/10.13182/NT92-A34651
Pouring of 100-kg-Scale Molten UO₂ into Sodium
Daniel Magallon, Hermann Hohmann, Hubert Schins
Nuclear Technology | Volume 98 | Number 1 | April 1992 | Pages 79-90
Technical Paper | Fast Reactor Safety / Nuclear Reactor Safety | doi.org/10.13182/NT92-A34652
Fuel Motion in Overpower Tests of Metallic Integral Fast Reactor Fuel
Edgar A. Rhodes, Theodore H. Bauer, George S. Stanford, James P. Regis, Charles E. Dickerman
Nuclear Technology | Volume 98 | Number 1 | April 1992 | Pages 91-99
Technical Paper | Fast Reactor Safety / Nuclear Reactor Safety | doi.org/10.13182/NT92-A34653
A Model for an Effective Equation of State of Irradiated Fast Reactor Fuel
Erhard A. Fischer
Nuclear Technology | Volume 98 | Number 1 | April 1992 | Pages 100-112
Technical Paper | Fast Reactor Safety / Nuclear Fuel Cycle | doi.org/10.13182/NT92-A34654
Sinusoidal Source Perturbation Experiments with a Breached Fuel Subassembly in the Experimental Breeder Reactor II
Kenny C. Gross, Robert V. Strain
Nuclear Technology | Volume 98 | Number 1 | April 1992 | Pages 113-123
Technical Paper | Fast Reactor Safety / Nuclear Fuel Cycle | doi.org/10.13182/NT92-A34655
Features of Postfailure Fuel Behavior in Transient Overpower and Transient Undercooled/Overpower Tests in the Transient Reactor Test Facility
Robert C. Doerner, Theodore H. Bauer, James A. Morman, John W. Holland
Nuclear Technology | Volume 98 | Number 1 | April 1992 | Pages 124-136
Technical Paper | Fast Reactor Safety / Nuclear Fuel Cycle | doi.org/10.13182/NT92-A34656

Number 2

Table of Contents
Comments on“Nuclear Fuel Reprocessing of (U,Pu)O₂ Fuel” (A. Palamalai, G. R. Balasubramanian)

Robust Optimal Control of Nuclear Reactors and Power Plants
Robert M. Edwards, Kwang Y. Lee, Asok Ray
Nuclear Technology | Volume 98 | Number 2 | May 1992 | Pages 137-148
Technical Paper | Fission Reactor | doi.org/10.13182/NT92-A34669
DF-4 Analysis Using SCDAP/RELAP5
Judith K. Hohorst, Chris M. Allison
Nuclear Technology | Volume 98 | Number 2 | May 1992 | Pages 149-159
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34670
Sensitivity, Uncertainty, and Importance Analysis of a Risk Assessment
Risto S. Andsten, Jussi K. Vaurio
Nuclear Technology | Volume 98 | Number 2 | May 1992 | Pages 160-170
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34671
Failure Probability of Axially Cracked Steam Generator Tubes: A Probabilistic Fracture Mechanics Model
Borut Mavko, Leon Cizelj
Nuclear Technology | Volume 98 | Number 2 | May 1992 | Pages 171-177
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34672
Crud Formation by Palladium Particles as Insoluble Residues
Kenzo Munakata, Hiroshi Sugai, Shigehiko Miyachi, Shouzo Yasu
Nuclear Technology | Volume 98 | Number 2 | May 1992 | Pages 178-187
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT92-A34673
Emulsions Stabilized by Precipitates of Zirconium and Tributyl Phosphate Degradation Products
Hiroshi Sugai, Kenzo Munakata, Shigehiko Miyachi, Shouzo Yasu
Nuclear Technology | Volume 98 | Number 2 | May 1992 | Pages 188-195
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT92-A34674
Estimate of the Crud Contribution to Shipping Cask Containment Requirements
Robert P. Sandoval, Robert E. Einziger, Hans Jordan, Anthony P. Malinauskas, Walter J. Mings
Nuclear Technology | Volume 98 | Number 2 | May 1992 | Pages 196-206
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT92-A34675
Analysis of Palladium Coatings to Remove Hydrogen Isotopes from Zirconium Fuel Rods in Canada Deuterium Uranium-Pressurized Heavy Water Reactors: Thermal and Neutron Diffusion Effects
Cynthia L. Stokes, Robert E. Buxbaum
Nuclear Technology | Volume 98 | Number 2 | May 1992 | Pages 207-216
Technical Paper | Material | doi.org/10.13182/NT92-A34676
Neutron Autoradiography of Trace Amounts of Gadolinium
Jing-Luen A. Shih, Robert M. Brugger†
Nuclear Technology | Volume 98 | Number 2 | May 1992 | Pages 217-223
Technical Paper | Radiation Biology and Medicine | doi.org/10.13182/NT92-A34677
An Analysis for the Failed Steam Generator Tube Plug
Hsu-Chieh Yeh, Robert F. Keating, R. Michael Roidt, L. E. Hochreiter
Nuclear Technology | Volume 98 | Number 2 | May 1992 | Pages 224-229
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34678
Semi-Markov Reliability Analysis of Alternating Systems in a Nuclear Power Plant
Kwang Nam Lee, Nam Zin Cho
Nuclear Technology | Volume 98 | Number 2 | May 1992 | Pages 230-241
Technical Paper | Reactor Operation | doi.org/10.13182/NT92-A34679
Electrochemical Decontamination of Metallic Surfaces Contaminated by Spent-Fuel Storage Pool Water
Prakash B. Chaudhary, Manohar G. Bhide
Nuclear Technology | Volume 98 | Number 2 | May 1992 | Pages 242-244
Technical Note | Nuclear Fuel Cycle | doi.org/10.13182/NT92-A34680
Consequences of Instability and Nonstoichiometry in High-Temperature Nuclear Fuels
Donald G. Schweitzer
Nuclear Technology | Volume 98 | Number 2 | May 1992 | Pages 245-252
Technical Note | Nuclear Fuel Cycle | doi.org/10.13182/NT92-A34681

Number 3

Table of Contents

The Reactor Physics Design of Gas-Cooled Cermet Reactors and Their Potential Application to Space Power Systems
S. N. Jahshan
Nuclear Technology | Volume 98 | Number 3 | June 1992 | Pages 257-276
Technical Paper | Fission Reactor | doi.org/10.13182/NT92-A34658
Accident Management for a Loss of Feedwater in a Pressurized Water Reactor
Carmelo Billa, Francesco D’Auria, Giorgio Maria Galassi
Nuclear Technology | Volume 98 | Number 3 | June 1992 | Pages 277-288
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34659
An Analysis of Feed-and-Bleed Cooling of a Pressurized Water Reactor
Min Lee, Jiing-Huae Wu
Nuclear Technology | Volume 98 | Number 3 | June 1992 | Pages 289-306
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34660
A Prototype Expert System for the Monitoring of Defected Nuclear Fuel Elements in Canada Deuterium Uranium Reactors
Brent J. Lewis, Russell J. Green, Christopher W. T. Che
Nuclear Technology | Volume 98 | Number 3 | June 1992 | Pages 307-321
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT92-A34661
An Epithermal Neutron Beam for Neutron Capture Therapy at the Missouri University Research Reactor
Robert M. Brugger, Jing-Luen A. Shih, Hungyuan B. Liu
Nuclear Technology | Volume 98 | Number 3 | June 1992 | Pages 322-332
Technical Paper | Radiation Biology and Medicine | doi.org/10.13182/NT92-A34662
Validation and Extension of a Correlation for Predicting Onset of Nucleate Boiling in Plate-Type Research Reactors
Efigenio Cubillos-Moreno, Mohamed Belhadj, Tunc Aldemir
Nuclear Technology | Volume 98 | Number 3 | June 1992 | Pages 333-348
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34663
Elementary Model to Predict the Pressure Loss Across a Spacer Grid Without a Mixing Vane
Nae-Hyun Kim, Sang Keun Lee, Kap Suk Moon
Nuclear Technology | Volume 98 | Number 3 | June 1992 | Pages 349-353
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34664
Bundle Critical Power Predictions Under Normal and Abnormal Conditions in Pressurized Water Reactors
Wen-Shan Lin, Bau-Shei Pei, Chien-Hsiung Lee
Nuclear Technology | Volume 98 | Number 3 | June 1992 | Pages 354-365
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34665
Application of Generation and Condensation Models to Predict Subcooled Boiling Void at Low Pressures
VIjay Chatoorgoon, Geoffrey R. Dimmick, Michael B. Carver, William N. Selander, Mamdouh Shoukri
Nuclear Technology | Volume 98 | Number 3 | June 1992 | Pages 366-378
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34666
Measurements of Gamma-Ray Shielding Properties of Ilmenite-Magnetite Concrete and Polyboron Slabs Using a ²⁵²Cf Source
F. U. Ahmed, S. I. Bhuiyan, A. S. Mollah, M. M. Rahman
Nuclear Technology | Volume 98 | Number 3 | June 1992 | Pages 379-386
Technical Note | Radiation Protection | doi.org/10.13182/NT92-A34667

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