ANS / Publications / Journals / Nuclear Technology

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT92-A34656

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT92-A34681

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT92-A34667