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Volume 111

Number 1 | Number 2 | Number 3

Number 1

A Parametric Study of the Steady-State Operational Characteristics of the Ohio State University Natural Circulation, Indirect-Cycle, Inherently Safe Boiling Water Reactor

Hikmet S. Aybar, Tunc Aldemir, Richard N. Christensen

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 1-22

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT95-A35140

An Estimation of Core Damage Frequency of a Pressurized Water Reactor During Midloop Operation Due to Loss of Residual Heat Removal

Chun-Chang Chao, Chi Ta Chen, Min Lee

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 23-33

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A35141

A Comparison of the RELAP5/MOD3 Code with the IIST Natural Circulation Experiments

Yuh-Ming Ferng, Chien-Hsiung Lee

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 34-45

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A35142

Predicting the Severity of Nuclear Power Plant Transients Using Nearest Neighbors Modeling Optimized by Genetic Algorithms on a Parallel Computer

Jie Lin, Yair Bartal, Robert E. Uhrig

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 46-62

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A35143

Effects of Different Parameters on the Densities of Uranium Dioxide and Uranium Dioxide-Gadolinium Oxide Fuels Produced by the Sol-Gel Technique

G. Gündüz, İ. Uslu, I. Önal, H. H. Durmazuçar, T. Öztürk, A. A. Akşit, B. Kopuz, F. Can, Ş. Can, R. Uzmen

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 63-69

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT95-A35144

Measured Insensitivity of Memory Devices to Various Nuclear Radiations

Alireza Behbahani, James N. Anno

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 70-79

Technical Paper / Material / dx.doi.org/10.13182/NT95-A35145

Evaporation Reduction from Tritiated Water Pools

M. T. Pauken, M. F. Dowling, B. K. Kamboj, S. M. Jeter, S. I. Abdel-Khalik

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 80-91

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35146

Application of Detonation Wave Theory to Subcritical Vapor Explosions

Luder Tibkin, Mahmoud El-Beshbeeshy, Riccardo Bonazza, Michael L. Corradini

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 92-104

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35147

Failed Fuel Detection in Reactor Coolant Using Radioiodine Measurement

R. K. Gopalakrishnan, P. M. Ravi, S. K. Prasad, M. R. Iyer

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 105-108

Technical Note / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT95-A35148

Nuclear Fuel Management Optimization Using Genetic Algorithms

Michael D. DeChaine, Madeline Anne Feltus

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 109-114

Technical Note / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT95-A35149

Application of Reliability-Centered Maintenance to Boiling Water Reactor Emergency Core Cooling Systems Fault-Tree Analysis

Young A. Choi, Madeline Anne Feltus

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 115-121

Technical Note / Reactor Operation / dx.doi.org/10.13182/NT95-A35150

Neutronics and Engineering Design of the Aqueous-Slurry Accelerator Transmutation of Waste Blanket

Carl A. Beard, John J. Buksa, Michael W. Cappiello, J. Wiley Davidson, Jay S. Elson, John R. Ireland, Robert A. Krakowski, Burt J. Krohn, William C. Sailor, Joseph L. Sapir

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 122-132

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT95-A35151

Long-Lived Waste Transmutation in Reactors

Jean Tommasi, Marc Delpech, Jean-Paul Grouiller, Alain Zaetta

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 133-148

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT111-133

Transmutation of High-Level Radioactive Waste by a Charged-Particle Accelerator

Hiroshi Takahashi

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 149-162

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT95-A35153

Vitrification of Fission Product Solutions: Investigation of the Effects of Noble Metals on the Fabrication and Properties of R7T7 Glass

M. Puyou, N. Jacquet-Francillon, J. P. Moncouyoux, C. Sombret, F. Teulon

Nuclear Technology / Volume 111 / Number 1 / July 1995 / Pages 163-168

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT95-A35154

Number 2

Estimation and Interpretation of keff Confidence Intervals in MCNP

Todd J. Urbatsch, R. Arthur Forster, Richard E. Prael, Richard J. Beckman

Nuclear Technology / Volume 111 / Number 2 / August 1995 / Pages 169-182

Technical Paper / Nuclear Criticality Safety Special / Fission Reactor / dx.doi.org/10.13182/NT95-A35128

Validation of KENO V.a with ENDF/B-V Cross Sections for 233U Systems

M. E. Dunn, B. Basoglu, C. L. Bentley, C. Haught, M. J. Plaster, A. D. Wilkinson, T. Yamamoto, H. L. Dodds

Nuclear Technology / Volume 111 / Number 2 / August 1995 / Pages 183-196

Technical Paper / Nuclear Criticality Safety Special / Fission Reactor / dx.doi.org/10.13182/NT95-A35129

Analyses of Hypothetical Nuclear Criticality Excursions in 10- and 20-MW Freezer/Sublimer Vessels

Chris F. Haught, W. C. Jordan, B. Basoglu, R. W. Brewer, A. D. Wilkinson, H. L. Dodds

Nuclear Technology / Volume 111 / Number 2 / August 1995 / Pages 197-218

Technical Paper / Nuclear Criticality Safety Special / Nuclear Criticality Safety / dx.doi.org/10.13182/NT95-A35130

Analysis of a Hypothetical Criticality Accident in a Waste Supercompactor

M. J. Plaster, B. Basoglu, C. L. Bentley, M. E. Dunn, A. E. Ruggles, A. D. Wilkinson, T. Yamamoto, H. L. Dodds

Nuclear Technology / Volume 111 / Number 2 / August 1995 / Pages 219-226

Technical Paper / Nuclear Criticality Safety Special / Nuclear Criticality Safety / dx.doi.org/10.13182/NT95-A35131

Improved Dose Estimates for Nuclear Criticality Accidents

Alan D. Wilkinson, B. Basoglu, C. L. Bentley, M. E. Dunn, Chris F. Haught, M. J. Plaster, T. Yamamoto, H. L. Dodds, Calvin M. Hopper

Nuclear Technology / Volume 111 / Number 2 / August 1995 / Pages 227-240

Technical Note / Nuclear Criticality Safety Special / Nuclear Criticality Safety / dx.doi.org/10.13182/NT95-A35132

Thermal Hydraulics of an External Water Wall Type Passive Containment Cooling System

Yoshiyuki Kataoka, Michio Murase, Tadashi Fujii, Kenji Tominaga

Nuclear Technology / Volume 111 / Number 2 / August 1995 / Pages 241-250

Technical Paper / Nuclear Criticality Safety Special / Fission Reactor / dx.doi.org/10.13182/NT95-A35133

Dynamic Stability of a Fluidized-Bed Nuclear Reactor

Volnei Borges, Marco Túllio De Vilhena

Nuclear Technology / Volume 111 / Number 2 / August 1995 / Pages 251-259

Technical Paper / Nuclear Criticality Safety Special / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A35134

Failure Mechanisms of Fuel Particle Coating for High-Temperature Gas-Cooled Reactors During the Coating Processes

Kazuo Minato, Hironobu Kikuchi, Kousaku Fukuda, Nobuyuki Suzuki, Hiroshi Tomimoto, Nobu Kitamura, Mitsunobu Kaneko

Nuclear Technology / Volume 111 / Number 2 / August 1995 / Pages 260-269

Technical Paper / Nuclear Criticality Safety Special / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT95-A35135

Three-Dimensional Neutron Flux Calculations for the VVER Pressure Vessel

Sergey I. Belousov, Krassimira D. Ilieva, Stoyan Y. Antonov

Nuclear Technology / Volume 111 / Number 2 / August 1995 / Pages 270-274

Technical Paper / Nuclear Criticality Safety Special / Material / dx.doi.org/10.13182/NT95-A35136

Flashing and Heat Transfer During Outsurge Transients in a Small Pressurizer

Mario De Salve, Giovanni Del Tin, Bruno Panella

Nuclear Technology / Volume 111 / Number 2 / August 1995 / Pages 275-282

Technical Paper / Nuclear Criticality Safety Special / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT95-A35137

Use of a Real-Time RELAP5 Model to Dynamically Test a Digital Feedwater Control System for a Boiling Water Reactor

J. A. Mowrey, S. I. Abdel-Khalik, K. W. Ross

Nuclear Technology / Volume 111 / Number 2 / August 1995 / Pages 283-302

Technical Paper / Nuclear Criticality Safety Special / Reactor Operation / dx.doi.org/10.13182/NT95-A35138

Number 3

Confinement of the Radiological Source Term During Beyond-Design-Basis Events in Future Pressurized Water Reactors

Guenther Kessler, Bernhard Kuczera, Joachim Ehrhardt, Georg Henneges, Werner Scholtyssek, Hans-Werner Wiese

Nuclear Technology / Volume 111 / Number 3 / September 1995 / Pages 305-318

Technical Paper / A New Light Water Reactor Safety Concept Special / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A15861

Long-Term Containment Thermal-Hyraulic Loads in Pressurized Water Reactor Core-Melt Accidents

Werner Scholtyssek

Nuclear Technology / Volume 111 / Number 3 / September 1995 / Pages 319-330

Technical Paper / A New Light Water Reactor Safety Concept Special / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A15862

Studies for the Staggered Pans Core Catcher

Günter Fieg, Manfred Möschke, Heinrich Werle

Nuclear Technology / Volume 111 / Number 3 / September 1995 / Pages 331-340

Technical Paper / A New Light Water Reactor Safety Concept Special / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A15863

Transient Experiments with Thermite Melts for a Core Catcher Concept Based on Water Addition from Below

Walter Tromm, Hans Alsmeyer

Nuclear Technology / Volume 111 / Number 3 / September 1995 / Pages 341-350

Technical Paper / A New Light Water Reactor Safety Concept Special / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A15864

Dynamic Loads from Reactor Pressure Vessel Core Melt-Through Under High Primary System Pressure

Günter Jacobs

Nuclear Technology / Volume 111 / Number 3 / September 1995 / Pages 351-357

Technical Paper / A New Light Water Reactor Safety Concept Special / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A15865

Severe Accident Containment Loads and Possible Design Concepts of Future Large Pressurized Water Reactors

Guenther Kessler, Josef Eibl

Nuclear Technology / Volume 111 / Number 3 / September 1995 / Pages 358-368

Technical Paper / A New Light Water Reactor Safety Concept Special / Fission Reactor / dx.doi.org/10.13182/NT95-A15866

Slug Impact Loading on the Vessel Head During a Postulated In-Vessel Steam Explosion in Pressurized Water Reactors—Assessments and Discussion of the Investigation Strategy

R. Krieg, T. Malmberg, G. Messemer, T. Stach, E. Stratmanns

Nuclear Technology / Volume 111 / Number 3 / September 1995 / Pages 369-385

Technical Paper / A New Light Water Reactor Safety Concept Special / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A15867

Passive Containment Cooling by Natural Air Convection

Franz-Josef Erbacher, Hans-Joachim Neitzel

Nuclear Technology / Volume 111 / Number 3 / September 1995 / Pages 386-394

Technical Paper / A New Light Water Reactor Safety Concept Special / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A15868

Containment Pressure Loads from Hydrogen Combustion in Unmitigated Severe Accidents

W. Breitung, R. Redlinger

Nuclear Technology / Volume 111 / Number 3 / September 1995 / Pages 395-419

Technical Paper / A New Light Water Reactor Safety Concept Special / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A15869

A Model for Structural Response to Hydrogen Combustion Loads in Severe Accidents

W. Breitung, R. Redlinger

Nuclear Technology / Volume 111 / Number 3 / September 1995 / Pages 420-425

Technical Paper / A New Light Water Reactor Safety Concept Special / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A15870

Feasibility Study for a Containment to Resist Core-Melt Accidents

Josef Butsch, Franz-Hermann Schlüter, Josef Eibl

Nuclear Technology / Volume 111 / Number 3 / September 1995 / Pages 426-436

Technical Paper / A New Light Water Reactor Safety Concept Special / Nuclear Reactor Safety / dx.doi.org/10.13182/NT95-A15871

 

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