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Volume 83

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Number 1

Table of Contents
Authors(Tien-Ko Wang, Szu-Li Chang, Shi-Ping Teng, Jorma Jokiniemi, Tsutomu Sakurai, Akira Takahashi, Niro Ishikawa, Yoshihide Komaki, Scott A. Comes, Paul J. Turinsky, Herbert Wieczorek, Bernhard Oser, Y. W. Wang, C. H. King, B. S. Pei, Nikolay Ivanov Kolev, S. M. Sami, M. Kraitem, Nicholas T. Saltos, Richard N. Christensen, Tunc Aldemir)
Creep Properties of Three Heats of Type 316 Stainless Steel for Elevated Temperature Nuclear Applications

Criticality Safety Evaluation for High-Density Spent-Fuel Storage Racks

Tien-Ko Wang, Szu-Li Chang, Shi-Ping Teng

Nuclear Technology / Volume 83 / Number 1 / October 1988 / Pages 5-15

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT88-A34170

The Growth of Hygroscopic Particles During Severe Core Melt Accidents

Jorma Jokiniemi

Nuclear Technology / Volume 83 / Number 1 / October 1988 / Pages 16-23

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT88-A34171

The Composition of NO_x Generated in the Dissolution of Uranium Dioxide

Tsutomu Sakurai, Akira Takahashi, Niro Ishikawa, Yoshihide Komaki

Nuclear Technology / Volume 83 / Number 1 / October 1988 / Pages 24-30

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT88-A34172

Out-of-Core Fuel Cycle Optimization for Nonequilibrium Cycles

Scott A. Comes, Paul J. Turinsky

Nuclear Technology / Volume 83 / Number 1 / October 1988 / Pages 31-48

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT88-A34173

Development and Active Demonstration of Acid Digestion of Plutonium- Bearing Waste

Herbert Wieczorek, Bernhard Oser

Nuclear Technology / Volume 83 / Number 1 / October 1988 / Pages 49-55

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT88-A34174

Identification of Two-Phase Flow Patterns by a Single Void Fraction Sensor

Y. W. Wang, C. H. King, B. S. Pei

Nuclear Technology / Volume 83 / Number 1 / October 1988 / Pages 56-64

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT88-A34175

IVA2 Verification: High-Pressure Gas Injection in a Liquid Pool

Nikolay Ivanov Kolev

Nuclear Technology / Volume 83 / Number 1 / October 1988 / Pages 65-80

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT88-A34176

Development of Computer Program DYNAM/US for Predicting Thermally Induced Flow Oscillations in Two-Phase Flow Systems

S. M. Sami, M. Kraitem

Nuclear Technology / Volume 83 / Number 1 / October 1988 / Pages 81-92

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT88-A34177

Determination of Transient Radial-Azimuthal Temperature Distributions in Fuel Bundles Under Loss-of-Coolant-Accident Conditions

Nicholas T. Saltos,* Richard N. Christensen, Tunc Aldemir

Nuclear Technology / Volume 83 / Number 1 / October 1988 / Pages 93-109

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT88-A34178

Number 2

Table of Contents
Authors(Harry A. Morewitz, Masahiro Matsumura, Tsuyoshi Misawa, Seiji Shiroya, Keiji Kanda, Tim H. J. J. van der Hagen, James C. Mailen, Donald J. Reif, Per G. Reinhall, Kwanhum Park, Robert W. Albrecht, John B. Rajan, Romesh Kumar, Donald R. Vissers, Ahmet Bayülken, V. F. Baston, K. J. Hofstetter, Richard F. Karuhn, P. Arora, P. Munshi, R. K. S. Rathore)
Nuclear Imperatives and Public Trust: Dealing with Radioactive Waste(Raymond L. Murray)
Nuclear Aerosol Science

Filtered Vented Containment Systems for Light Water Reactors

Harry A. Morewitz

Nuclear Technology / Volume 83 / Number 2 / November 1988 / Pages 117-133

Technical Paper / Critical Review / dx.doi.org/10.13182/NT88-A34155

Assessment of Long-Term Reliability of Pressurized Water Reactor Plants Based on Power Generation Statistics (Up to 1987)

Masahiro Matsumura

Nuclear Technology / Volume 83 / Number 2 / November 1988 / Pages 134-161

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT88-A34156

Study on Criticality of a Light Water Moderated and Reflected Coupled Core with Highly Enriched Uranium Fuel

Tsuyoshi Misawa, Seiji Shiroya, Keiji Kanda

Nuclear Technology / Volume 83 / Number 2 / November 1988 / Pages 162-170

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT88-A34157

Experimental and Theoretical Evidence for a Short Effective Fuel Time Constant in a Boiling Water Reactor

Tim H. J. J. van der Hagen

Nuclear Technology / Volume 83 / Number 2 / November 1988 / Pages 171-181

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT88-A34158

Secondary Purex Solvent Cleanup: Laboratory Development

James C. Mailen

Nuclear Technology / Volume 83 / Number 2 / November 1988 / Pages 182-189

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT88-A34159

Canyon Solvent Cleaning with Activated Alumina

Donald J. Reif

Nuclear Technology / Volume 83 / Number 2 / November 1988 / Pages 190-196

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT88-A34160

Analysis of Mechanical Bowing Phenomena of Fuel Assemblies in Passively Safe Advanced Liquid-Metal Reactors

Per G. Reinhall, Kwanhum Park, Robert W. Albrecht

Nuclear Technology / Volume 83 / Number 2 / November 1988 / Pages 197-204

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT88-A34161

Improved Treatment/Disposal of Reactive Metals

John B. Rajan, Romesh Kumar, Donald R. Vissers

Nuclear Technology / Volume 83 / Number 2 / November 1988 / Pages 205-211

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT88-A34162

The Economic Impact of the Utilization of Nuclear Power Plant Condensation Heat

Ahmet Bayülken

Nuclear Technology / Volume 83 / Number 2 / November 1988 / Pages 212-215

Technical Paper / Economic / dx.doi.org/10.13182/NT88-A34163

Characterization of Reaction Gases and Aerosols from Underwater Plasma Arc Cutting Demonstration Tests at Three Mile Island Unit 2

V. F. Baston, K. J. Hofstetter, Richard F. Karuhn

Nuclear Technology / Volume 83 / Number 2 / November 1988 / Pages 216-227

Technical Paper / Material / dx.doi.org/10.13182/NT88-A34164

Higher Order Tomographic Filters for Nondestructive Testing Purposes

P. Arora, P. Munshi, R. K. S. Rathore

Nuclear Technology / Volume 83 / Number 2 / November 1988 / Pages 228-230

Technical Note / Technique / dx.doi.org/10.13182/NT88-A34165

Number 3

Table of Contents
Authors(Lance J. Agee, Peter J. Jensen, V. K. (Bindi) Chexal, Jason Chao, William H. Layman, M. P. Paulsen, B. E. Griebenow, L. R. Feinauer, J. H. McFadden, Peter J. Jensen, Jason Chao, V. K.(Bindu) Chexal, William H. Layman, Gary Vine, Peter J. Jensen, Adi R. Dastur, Steven J. Ganthner, A. Frank Wenger, James F. Harrison, J. J. Martínez Caballero, Pablo García Sedano, Jorge Arpa, Jose Ramos, Juan R. Villar, Steven P. Nesbit, Richard J. Gerling, Gregg B. Swindlehurst, Mansur A. Alammar, Ronald V. Furia, Jimmy H. Chin, Chandrakant B. Mehta, Joseph O. Erb, James G. Miller, Shie-Jeng Peng, John Sorensen)
Technical Reviewer

Overview of 1986–1987 RETRAN Activity

Lance J. Agee

Nuclear Technology / Volume 83 / Number 3 / December 1988 / Pages 241-251

Overview / Fifth International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT88-A34139

RETRAN Application for Issue Resolution

Peter J. Jensen, V. K. Chexal, Jason Chao, William H. Layman

Nuclear Technology / Volume 83 / Number 3 / December 1988 / Pages 252-273

Technical Paper / Fifth International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT88-A34140

Features of the RETRAN-03 Computer Code

M. P. Paulsen, B. E. Griebenow, L. R. Feinauer, J. H. McFadden, Peter J. Jensen

Nuclear Technology / Volume 83 / Number 3 / December 1988 / Pages 274-288

Technical Paper / Fifth International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT88-A34141

An Analysis of the Chernobyl Accident Using RETRAN-02/MOD3

Jason Chao, V. K. Chexal, William H. Layman, Gary Vine, Peter J. Jensen, Adi R. Dastur

Nuclear Technology / Volume 83 / Number 3 / December 1988 / Pages 289-301

Technical Paper / Fifth International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT88-A34142

Results of Carolina Power and Light Company’s Analysis of Brunswick Unit 1 Start-Up Tests Using RETRAN

Steven J. Ganthner, A. Frank Wenger

Nuclear Technology / Volume 83 / Number 3 / December 1988 / Pages 302-309

Technical Paper / Fifth International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT88-A34143

Qualification of RETRAN for Simulator Applications

James F. Harrison

Nuclear Technology / Volume 83 / Number 3 / December 1988 / Pages 310-324

Technical Paper / Fifth International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT88-A34144

Qualification of a RETRAN-02 Model for Cofrentes

J. J. Martínez Caballero, Pablo García Sedano

Nuclear Technology / Volume 83 / Number 3 / December 1988 / Pages 325-333

Technical Paper / Fifth International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT88-A34145

RETRAN Applications at Florida Power & Light to Support Operations and Training

Jorge Arpa, Jose Ramos, Juan R. Villar

Nuclear Technology / Volume 83 / Number 3 / December 1988 / Pages 334-343

Technical Paper / Fifth International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT88-A34146

Qualification of the Oconee RETRAN Model by Comparison with Plant Transient Data

Steven P. Nesbit, Richard J. Gerling, Gregg B. Swindlehurst

Nuclear Technology / Volume 83 / Number 3 / December 1988 / Pages 344-352

Technical Paper / Fifth International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT88-A34147

Oyster Creek RETRAN Licensing Model Development

Mansur A. Alammar, Ronald V. Furia, Jimmy H. Chin, Chandrakant B. Mehta

Nuclear Technology / Volume 83 / Number 3 / December 1988 / Pages 353-366

Technical Paper / Fifth International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT88-A34148

RETRAN Modeling of the Pressurized Water Reactor Control Rod Ejection Transient

Joseph O. Erb, James G. Miller

Nuclear Technology / Volume 83 / Number 3 / December 1988 / Pages 367-373

Technical Paper / Fifth International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT88-A34149

Boiling Water Reactor Core Stability Analysis with RETRAN

Shie-Jeng Peng

Nuclear Technology / Volume 83 / Number 3 / December 1988 / Pages 374-382

Technical Paper / Fifth International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT88-A34150

Boiling Water Reactor Stability Analysis with RETRAN

John Sorensen

Nuclear Technology / Volume 83 / Number 3 / December 1988 / Pages 383-395

Technical Paper / Fifth International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT88-A34151