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Volume 61

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Number 1

Table of Contents
Authors(Mamoru Konomura, Yoshiaki Oka, Shigehiro An, Karl Heinemann, Ralf Hille, Kurt Jürgen Vogt, J. Louis Tylee, Jeffrey Rest, Chang Hyo Kim, Samuel H. Levine, Masumichi Koizumi, Katsuyuki Ohtsuka, Hiroto Isagawa, Hideo Akiyama, Akio Todokoro, K. Hilpert, R. Odoj, H. W. Nürnberg, S. H. Yeh, Alice Y. Ying, J. Weisman, Osamu Kuriyama, Takao Koyama, Makoto Kikuchi, G. R. Fenske, R. B. Poeppel, J. E. Emerson, P. M. Chapello, S. G. Das, R. H. Sevy, Bryce L. Shriver, Thomas G. Hook, H. Deuber, J. G. Wilhelm, Yuji Ishiguro, Daniel Neupert, Peter Demtröder)
Two-Phase Flow Dynamics(Sanjoy Baneijee)
Cogeneration and District Heating—An Energy Efficiency Partnership(Bruce Rankin)
Heat Transfer and Fluid Flow in Nuclear Systems(G. B. Melese-d’Hospital)
Adsorption from Aqueous Solutions(Arthur L. Reesman)
International Advances in Nondestructive Testing (Vol. 8)(Otto Buck)
Nuclear Myths and Realities: India’s Dilemma(John A. Wethington, Jr.)

The Effect of Coolant Orificing on the Core Performance of a Heterogeneous Liquid-Metal Fast Breeder Reactor

Mamoru Konomura, Yoshiaki Oka, Shigehiro An

Nuclear Technology / Volume 61 / Number 1 / April 1983 / Pages 7-16

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT83-A33138

An Emergency Measurement System for the Rapid Assessment of Environmental Exposure

Karl Heinemann, Ralf Hille, Kurt Jürgen Vogt

Nuclear Technology / Volume 61 / Number 1 / April 1983 / Pages 17-24

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT83-A33139

Simple Reactor Model Simulation of a LOFT ATWS Event

J. Louis Tylee

Nuclear Technology / Volume 61 / Number 1 / April 1983 / Pages 25-32

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT83-A33140

Evaluation of Volatile and Gaseous Fission Product Behavior in Water Reactor Fuel Under Normal and Severe Core Accident Conditions

Jeffrey Rest

Nuclear Technology / Volume 61 / Number 1 / April 1983 / Pages 33-48

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT83-A33141

A Modified Borresen Coarse-Mesh Computation for a Three-Dimensional Pressurized Water Reactor Benchmark Problem

Chang Hyo Kim, Samuel H. Levine

Nuclear Technology / Volume 61 / Number 1 / April 1983 / Pages 49-54

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT83-A33142

Development of a Process for the Co-Conversion of Pu-U Nitrate Mixed Solutions to Mixed-Oxide Powder Using a Microwave Heating Method

Masumichi Koizumi, Katsuyuki Ohtsuka, Hiroto Isagawa, Hideo Akiyama, Akio Todokoro

Nuclear Technology / Volume 61 / Number 1 / April 1983 / Pages 55-70

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT83-A33143

Mass Spectrometric Study of the Potential of Al₂O₃/SiO₂ Additives for the Retention of Cesium in Coated Particles

K. Hilpert, R. Odoj, H. W. Nürnberg

Nuclear Technology / Volume 61 / Number 1 / April 1983 / Pages 71-77

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT83-A33144

An Automated Procedure for Selecting Boiling Water Reactor Refueling Policies Following Operational Problems or Changes

S. H. Yeh, Alice Y. Ying, J. Weisman

Nuclear Technology / Volume 61 / Number 1 / April 1983 / Pages 78-92

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT83-A33145

Decontamination of Radioactive Metal Surfaces by Plasma Arc Gouging

Osamu Kuriyama, Takao Koyama, Makoto Kikuchi

Nuclear Technology / Volume 61 / Number 1 / April 1983 / Pages 93-99

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT83-A33146

Effect of Helium Pressure on the Response of Unirradiated UO₂ Subjected to Thermal Transients

G. R. Fenske, R. B. Poeppel, J. E. Emerson, P. M. Chapello, S. G. Das, R. H. Sevy

Nuclear Technology / Volume 61 / Number 1 / April 1983 / Pages 100-112

Technical Paper / Material / dx.doi.org/10.13182/NT83-A33147

Temperature-Dependent Microhardness of A533-B Reactor Pressure Vessel Steels

Bryce L. Shriver, Thomas G. Hook

Nuclear Technology / Volume 61 / Number 1 / April 1983 / Pages 113-117

Technical Paper / Material / dx.doi.org/10.13182/NT83-A33148

Investigations on the Improvement of the Iodine Filtration Concept of Pressurized Water Reactors

H. Deuber, J. G. Wilhelm

Nuclear Technology / Volume 61 / Number 1 / April 1983 / Pages 118-120

Technical Note / Nuclear Safety / dx.doi.org/10.13182/NT83-A33149

A Liquid-Metal Fast Breeder Reactor Fueling Concept for Thorium Utilization and Improved Inherent Safety

Yuji Ishiguro

Nuclear Technology / Volume 61 / Number 1 / April 1983 / Pages 121-126

Technical Note / Fuel Cycle / dx.doi.org/10.13182/NT83-A33150

Method for the Sealing and Decontamination of Radioactive and Radioactively Contaminated Components and Materials

Daniel Neupert, Peter Demtröder

Nuclear Technology / Volume 61 / Number 1 / April 1983 / Pages 127-128

Technical Note / Radioactive Waste Management / dx.doi.org/10.13182/NT83-A33151

Number 2

Table of Contents
Authors(Lance J. Agee, M. P. Paulsen, E. D. Hughes, E. D. Hughes, K. R. Katsma, Clayton S. Miller, James Robert White, Richard D. Hentzen, Yoshinori Naruko, Toshihisa Ishida, Yoshimi Tanaka, Yoshiaki Futamura, A. A. Farooq Ansari, Kevin J. Burns, Douglas K. Beller, Quazi A. Haque, Stephen P. Schultz, Mario V. Bonaca, Albert Gharakhani, Richard W. Sterner, Jason Chao, V. K. (Bindi) Chexal, William H. Layman, David A. Rautmann, Craig E. Peterson, Larry W. Cress, Salvador Ranatza, Jr., T. Gary Broughton, N. G. Trikouros, Karel L. Papez, Daniel H. Risher, Michael E. Garrett, Samuel L. Forkner, T. A. Keys, George W. Perry, M. Wesley Waddell, Jr., Karl Hornyik, Joseph A. Naser, Neil M. Howard, Mitchell J. Krasnopoler, Lawrence A. Casper, Arvid M. Jensen, Kendall G. Magill, Penny M. Wikoff, William T. Li, Ching L. Wu, Osvaldo Fiorella, Manlio Mangia, Elio Oliveri)
Heat Conduction(Wilhelm G. Wolfer)
Safety Aspects of Fuel Behaviour in Off-Normal and Accident Conditions(A. R. Wazzan)
Radiation Chemistry of Hydrocarbons(Joseph Silverman)
Proceedings of the 36th Industrial Waste Conference—Purdue University(Stephen G. Margolis)
Radiochemistry, Hot Atoms, and Physical Chemistry(Jeffrey I. Steinfeld)

RETRAN Overview

Lance J. Agee

Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 143-152

Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33186

RETRAN Nonequilibrium Two-Phase Flow Model for Operational Transient Analyses

M. P. Paulsen, E. D. Hughes

Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 153-166

Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33187

Numerical Solution Method Improvements for RETRAN

E. D. Hughes, K. R. Katsma

Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 167-180

Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33188

RETRAN-02 Calculations of Operational Transients in the Loss-of-Fluid Test Facility

Clayton S. Miller, James Robert White, Richard D. Hentzen

Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 181-192

Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33189

RETRAN Safety Analyses of the Nuclear-Powered Ship Mutsu

Yoshinori Naruko, Toshihisa Ishida, Yoshimi Tanaka, Yoshiaki Futamura

Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 193-204

Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33190

Prediction of GE-Atlas Transient Boiling Transition Data Using RETRAN-02/RETRAN-15F

A. A. Farooq Ansari, Kevin J. Burns, Douglas K. Beller, Quazi A. Haque, Stephen P. Schultz

Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 205-211

Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33191

RETRANS’s Role in the Development of Northeast Utilities’ Analytical Capabilities

Mario V. Bonaca, Albert Gharakhani, Richard W. Sterner

Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 212-223

Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33192

RETRAN-02 and DYNODE-P Analyses of a Steam Generator Tube Break Transient

Jason Chao, V. K. (Bindi) Chexal, William H. Layman, David A. Rautmann, Craig E. Peterson, Larry W. Cress

Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 224-237

Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33193

RETRAN-02 Analysis of Arkansas Nuclear One Unit 2 Tests

Salvador Ranatza, Jr.

Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 238-252

Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33194

RETRAN Analyses for Improving Plant Procedures and Operator Training

T. Gary Broughton, N. G. Trikouros

Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 253-259

Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33195

LOFTRAN/RETRAN Comparison Calculations for a Postulated Loss-of-Feedwater ATWS in the Sizewell ‘B’ PWR

Karel L. Papez, Daniel H. Risher

Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 260-275

Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33196

Qualification of a RETRAN-02 Model for Boiling Water Reactor Transient Analysis

Michael E. Garrett, Samuel L. Forkner, T. A. Keys, George W. Perry, M. Wesley Waddell, Jr.

Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 276-295

Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33197

Boiling Water Reactor Stability Analysis with RETRAN

Karl Hornyik

Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 296-312

Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33198

Evaluation of RETRAN-02 Options with Peach Bottom Data

Joseph A. Naser

Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 313-328

Technical Paper / Second International RETRAN Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33199

Simplified Tornado Depressurization Design Methods for Nuclear Power Plants

Neil M. Howard, Mitchell J. Krasnopoler

Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 329-337

Technical Paper / Second International RETRAN Meeting / Fission reactor / dx.doi.org/10.13182/NT83-A33200

Deactivation of Silver Zeolite Adsorbers by Airborne Organics

Lawrence A. Casper, Arvid M. Jensen, Kendall G. Magill, Penny M. Wikoff

Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 338-343

Technical Paper / Second International RETRAN Meeting / Nuclear Safety / dx.doi.org/10.13182/NT83-A33201

Analysis of Creep for Nuclear Waste Storage in a Salt Formation

William T. Li, Ching L. Wu

Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 344-352

Technical Paper / Second International RETRAN Meeting / Radioactive Waste Management / dx.doi.org/10.13182/NT83-A33202

Optimal Step Assays and Flow Rates in Gaseous Diffusion Squared-Off Cascades for Uranium Enrichment

Osvaldo Fiorella, Manlio Mangia, Elio Oliveri

Nuclear Technology / Volume 61 / Number 2 / May 1983 / Pages 353-361

Technical Paper / Second International RETRAN Meeting / Radioisotopes and Isotope / dx.doi.org/10.13182/NT83-A33203

Number 3

Table of Contents
Authors(Norbert G. Hoogen, Erich R. Merz, William D. Burch, W. S. Groenier, E. J. Detilleux, Werner Hild, L. Geens, Rainer P. Conrad, Cesare Merlini, Alfred-W. Mehner, J. M. Leblanc, Serge M. Orlowski, Heinz Dworschak, Brian A. Hunt, Francesco Mannone, Francis Mousty, Bernd K. Buchheim, Hans Bunschi, Franz J. Hoop, James Fitzpatrick, Hans- Urs Zwicky, Ian M. Böhringer, Ferdinand Petrik, Dieter O. Bedenig, Jean F. Lefevre, Milan Hrovat, Karl- Gerhard Hackstein, Hans Huschka, H. A. Pirk, Thomas Schmidt-Hansberg, Yukiharu Ohga, Winfried Amian, Detlev Stöver, Ziad H. Kodah, Samuel H. Levine, Antony E. Hughes, J. Angwn C. Marples, A. Marshall Stoneham, Alireza Haghighat, Maurice A. Robkin, Manuel G. Vigil, Amado A. Trujillo, H. Richard Yoshimura, John Brian Ainscough, David Norman Coucill, David Anthony Howl, Arne Jensen, Ib Misfeldt, Kazuo Arakawa, Naohiro Hayakawa, Hiroshi Nakanishi, Toshiaki Ohe, Akira Nakaoka, V. V. Athani, L. Vijay kumar)
The Temporary Worker in the Nuclear Power Industry: An Equity Analysis(Charles B. Meinhold)
Radiation Heat Transfer Notes(J. N. Anno)
Atomic Energy(K. Almenas)

Evaluation of Potential Head-End Procedures for Graphite-Containing Fuel Elements

Norbert G. Hoogen, Erich R. Merz

Nuclear Technology / Volume 61 / Number 3 / June 1983 / Pages 380-387

Technical Paper / New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Chemical Processing / dx.doi.org/10.13182/NT83-A33160

Reprocessing in Breeder Fuel Cycles

William D. Burch, W. S. Groenier

Nuclear Technology / Volume 61 / Number 3 / June 1983 / Pages 388-397

Technical Paper / New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Nuclear Fuel / dx.doi.org/10.13182/NT83-A33161

Reprocessing of Plutonium-Enriched Light Water Reactor Fuels

E. J. Detilleux, Werner Hild, L. Geens

Nuclear Technology / Volume 61 / Number 3 / June 1983 / Pages 398-402

Technical Paper / New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Nuclear Fuel / dx.doi.org/10.13182/NT83-A33162

Irradiation Performance of Advanced Coated Particles for High-Temperature Gas-Cooled Reactor Fuel Cycles

Rainer P. Conrad, Cesare Merlini, Alfred-W. Mehner

Nuclear Technology / Volume 61 / Number 3 / June 1983 / Pages 403-415

Technical Paper / New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Nuclear Fuel / dx.doi.org/10.13182/NT83-A33163

Plutonium-Enriched Thermal Fuel Production Experience in Belgium

J. M. Leblanc

Nuclear Technology / Volume 61 / Number 3 / June 1983 / Pages 416-422

Technical Paper / New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Nuclear Fuel / dx.doi.org/10.13182/NT83-A33164

The Radioactive Waste Management Program of the Commission of the European Communities: Past, Present, and Future Trends

Serge M. Orlowski

Nuclear Technology / Volume 61 / Number 3 / June 1983 / Pages 423-431

Technical Paper / New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Radioactive Waste Management / dx.doi.org/10.13182/NT83-A33165

Incentives for Integrating an Alpha Waste Management Strategy into the Fuel Cycle

Heinz Dworschak, Brian A. Hunt, Francesco Mannone, Francis Mousty

Nuclear Technology / Volume 61 / Number 3 / June 1983 / Pages 432-443

Technical Paper / New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Radioactive Waste Management / dx.doi.org/10.13182/NT83-A33166

Methodology for a Consequence Analysis of a Nuclear Waste Disposal Facility

Bernd K. Buchheim, Hans Bunschi, and, Franz J. Hoop, James Fitzpatrick

Nuclear Technology / Volume 61 / Number 3 / June 1983 / Pages 444-449

Technical Paper / New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Radioactive Waste Management / dx.doi.org/10.13182/NT83-A33167

The Decontamination of Soft-Plated Nickel Surfaces Compared to Alternative Surface Materials Used in Radioactive Transport and Storage Containers

Hans-Urs Zwicky, Ian M. Böhringer,*, Ferdinand Petrik, Dieter O. Bedenig

Nuclear Technology / Volume 61 / Number 3 / June 1983 / Pages 450-454

Technical Paper / New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Radioactive Waste Management / dx.doi.org/10.13182/NT83-A33168

Nuclear Waste Management Policy in France

Jean F. Lefevre

Nuclear Technology / Volume 61 / Number 3 / June 1983 / Pages 455-459

Technical Paper / New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Radioactive Waste Management / dx.doi.org/10.13182/NT83-A33169

Highly Dense Graphite Matrix: A New Material for the Conditioning of Radioactive Wastes

Milan Hrovat, Karl-Gerhard Hackstein, Hans Huschka, H. A. Pirk, Thomas Schmidt-Hansberg

Nuclear Technology / Volume 61 / Number 3 / June 1983 / Pages 460-464

Technical Paper / New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Radioactive Waste Management / dx.doi.org/10.13182/NT83-A33170

A Computer Program for Assessment of Emergency Operation Procedures Under Non-LOCA Transient Conditions in BWRs

Yukiharu Ohga

Nuclear Technology / Volume 61 / Number 3 / June 1983 / Pages 465-474

Technical Paper / New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Nuclear Safety / dx.doi.org/10.13182/NT83-A33171

Diffusion of Silver and Cesium in Silicon-Carbide Coatings of Fuel Particles for High-Temperature Gas-Cooled Reactors

Winfried Amian, Detlev Stöver

Nuclear Technology / Volume 61 / Number 3 / June 1983 / Pages 475-486

Technical Paper / New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Nuclear Fuel / dx.doi.org/10.13182/NT61-475

Optimized Depletion of Lumped Burnable Poisons in Pressurized Water Reactors

Ziad H. Kodah, Samuel H. Levine

Nuclear Technology / Volume 61 / Number 3 / June 1983 / Pages 487-495

Technical Paper / New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Nuclear Fuel / dx.doi.org/10.13182/NT83-A33173

The Significance of Leach Rates in Determining the Release of Radioactivity from Vitrified Nuclear Waste

Antony E. Hughes, J. Angwin C. Marples, A. Marshall Stoneham

Nuclear Technology / Volume 61 / Number 3 / June 1983 / Pages 496-502

Technical Paper / New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Radioactive Waste Management / dx.doi.org/10.13182/NT83-A33174

Actinide Hazard Reduction by Partitioning and Transmutation in a Coupled Reactor System

Alireza Haghighat, Maurice A. Robkin

Nuclear Technology / Volume 61 / Number 3 / June 1983 / Pages 503-513

Technical Paper / New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Radioactive Waste Management / dx.doi.org/10.13182/NT83-A33175

Measured Thermal Response of Full-Scale Spent Fuel Cask to a Torch Environment

Manuel G. Vigil, Amado A. Trujillo, H. Richard Yoshimura

Nuclear Technology / Volume 61 / Number 3 / June 1983 / Pages 514-520

Technical Paper / New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Radioactive Waste Management / dx.doi.org/10.13182/NT83-A33176

Preliminary Study of Cost Benefits Associated with Duplex Fuel Pellets of the LOWI Type

John Brian Ainscough*, David Norman Coucill, David Anthony Howl, Arne Jensen, Ib Misfeldt

Nuclear Technology / Volume 61 / Number 3 / June 1983 / Pages 521-532

Technical Paper / New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Economic / dx.doi.org/10.13182/NT83-A33177

Radiation-Induced Gas Evolution from Commercial Lubricant Base Oil

Kazuo Arakawa, Naohiro Hayakawa, Hiroshi Nakanishi

Nuclear Technology / Volume 61 / Number 3 / June 1983 / Pages 533-539

Technical Paper / New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Material / dx.doi.org/10.13182/NT83-A33178

Generalization of Radioiodine Adsorption on Geological Materials

Toshiaki Ohe, Akira Nakaoka

Nuclear Technology / Volume 61 / Number 3 / June 1983 / Pages 540-546

Technical Paper / New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Radiation Biology and Environment / dx.doi.org/10.13182/NT83-A33179

Digital Simulation of the Pressurizer in a Pressurized Water Nuclear Reactor

V. V. Athani, L. Vijaykumar

Nuclear Technology / Volume 61 / Number 3 / June 1983 / Pages 547-549

Technical Note / New Directions in Nuclear Energy with Emphasis on Fuel Cycles / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33180