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Volume 68

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Number 1

Table of Contents
Authors(Charles W. Bagnal, Jr., Gerard P. Cavanaugh, Robert P. Harris, Regis A. Matzie, Laszlo B. Tarko, Howard Ocken, Per Hedemann Jensen, Ian J. Hastings, Elio Mizzan, Alan M. Ross, John R. Kelm, Real J. Chenier, D. H. Rose, J. Novak, Claudio Ronchi, Jacques van de Laar, Hubert Blank, Tetsuo Fukasawa, Koichi Chino, Osamu Kuriyama, Fumio Kawamura, Hideo Yusa, Bernard L. Cohen, K. Tasaka, M. Suzuki, Y. Anoda, Y. Koizumi, T. Yonomoto, H. Kumamaru, H. Nakamura, M. Shiba, Genichi Matsumoto, Soichi Doi, Kohei Ohkubo, Yasushi Ikeda, Günther Hessel, Hans-Erich Köppen, Peter Liewers, Peter Schumann, Frank-Peter Weiβ)

Reduction in Reactor Vessel Irradiation Through Fuel Management

Charles W. Bagnal, Jr., Gerard P. Cavanaugh, Robert P. Harris, Regis A. Matzie, Laszlo B. Tarko

Nuclear Technology / Volume 68 / Number 1 / January 1985 / Pages 7-17

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33562

Reducing the Cobalt Inventory in Light Water Reactors

Howard Ocken

Nuclear Technology / Volume 68 / Number 1 / January 1985 / Pages 18-28

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33563

Shielding Factors for Gamma Radiation from Activity Deposited on Structures and Ground Surfaces

Per Hedemann Jensen

Nuclear Technology / Volume 68 / Number 1 / January 1985 / Pages 29-39

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT85-A33564

Postirradiation Behavior of UO₂ Fuel II: Fragments at 175 to 275°C in Air

Ian J. Hastings, Elio Mizzan, Alan M. Ross, John R. Kelm, Real J. Chenier, D. H. Rose, J. Novak

Nuclear Technology / Volume 68 / Number 1 / January 1985 / Pages 40-47

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT85-A33565

The Sodium-Bonding Pin Concept for Advanced Fuels. Part III: Calculations of the Swelling Performance

Claudio Ronchi, Jacques van de Laar, Hubert Blank

Nuclear Technology / Volume 68 / Number 1 / January 1985 / Pages 48-65

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT85-A33566

Incineration of Ion Exchange Resins Using Concentric Burners

Tetsuo Fukasawa, Koichi Chino, Osamu Kuriyama, Fumio Kawamura, Hideo Yusa

Nuclear Technology / Volume 68 / Number 1 / January 1985 / Pages 66-72

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT85-A33567

A Simple Probabilistic Risk Analysis for High-Level Waste Repositories

Bernard L. Cohen

Nuclear Technology / Volume 68 / Number 1 / January 1985 / Pages 73-76

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT85-A33568

ROSA-III Double-Ended Break Test Series for a Loss-of-Coolant Accident in a Boiling Water Reactor

K. Tasaka, M. Suzuki, Y. Anoda, Y. Koizumi, T. Yonomoto, H. Kumamaru, H. Nakamura, M. Shiba

Nuclear Technology / Volume 68 / Number 1 / January 1985 / Pages 77-93

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33569

Neutron Radiography with a Sealed-Tube Neutron Generator in a Hot Laboratory Water Pool at Nagoya University

Genichi Matsumoto, Soichi Doi, Kohei Ohkubo, Yasushi Ikeda

Nuclear Technology / Volume 68 / Number 1 / January 1985 / Pages 94-101

Technical Paper / Analyse / dx.doi.org/10.13182/NT85-A33570

Development of Nuclear Power Plant Noise Diagnostics into a Process-Measuring Method

Günther Hessel, Hans-Erich Köppen, Peter Liewers, Peter Schumann, Frank-Peter Weiß

Nuclear Technology / Volume 68 / Number 1 / January 1985 / Pages 102-110

Technical Note / Fission Reactor / dx.doi.org/10.13182/NT85-A33571

Number 2

Table of Contents
Authors(Jean Befre, Joël Branchu, Charles Gigarel, Henri Noël, Francesco Granito, Pierre Pouderoux, Henri Noël, Gilbert Pasqualini, Joël Branchu, Charles Gigarel, Kurt Ebbinghaus, Jean-Paul Crette, Thierry Zuber, Eduard Hofer, Vijen Javeri, Horst Löffler, Dankward F. Struwe, William E. Vesely, Thomas C. Davis, Ansar Parvez, Soon Heung Chang, Won Jin Cho, Joe E. Dahlquist, Fred S. Gunnerson, Ralph A. Nelson, Erik Johansson)
Preface: Fabrication of Components of the Creys-Malville Plant(A. Baer)

Superphénix 1 at Creys-Malville: Overall Nuclear Steam Supply System Coordination and Construction by Novatome-Nira

Jean Befre

Nuclear Technology / Volume 68 / Number 2 / February 1985 / Pages 125-134

Technical Paper / Fabrication of Components of the Creys-Malville Plant / Fission Reactor / dx.doi.org/10.13182/NT85-A33548

Superphénix 1 Reactor Block Fabrication

Joël Branchu, Charles Gigarel

Nuclear Technology / Volume 68 / Number 2 / February 1985 / Pages 135-145

Technical Paper / Fabrication of Components of the Creys-Malville Plant / Fission Reactor / dx.doi.org/10.13182/NT85-A33549

Superphénix 1 Intermediate Heat Exchanger Fabrication

Henri Noël, Francesco Granito, Pierre Pouderoux

Nuclear Technology / Volume 68 / Number 2 / February 1985 / Pages 146-152

Technical Paper / Fabrication of Components of the Creys-Malville Plant / Fission Reactor / dx.doi.org/10.13182/NT85-A33550

Fabrication and Testing of Main Sodium Pumps of Superphénix 1

Henri Noël, Gilbert Pasqualini

Nuclear Technology / Volume 68 / Number 2 / February 1985 / Pages 153-159

Technical Paper / Fabrication of Components of the Creys-Malville Plant / Fission Reactor / dx.doi.org/10.13182/NT85-A33551

Superphénix 1 Primary Handling System Fabrication and Testing

Joël Branchu, Charles Gigarel, Kurt Ebbinghaus

Nuclear Technology / Volume 68 / Number 2 / February 1985 / Pages 160-170

Technical Paper / Fabrication of Components of the Creys-Malville Plant / Fission Reactor / dx.doi.org/10.13182/NT85-A33552

Superphénix 1 Steam Generator Fabrication

Jean-Paul Crette, Thierry Zuber

Nuclear Technology / Volume 68 / Number 2 / February 1985 / Pages 171-179

Technical Paper / Fabrication of Components of the Creys-Malville Plant / Fission Reactor / dx.doi.org/10.13182/NT85-A33553

A Survey of Expert Opinion and Its Probabilistic Evaluation for Specific Aspects of the SNR-300 Risk Study

Eduard Hofer, Vijen Javeri, Horst Löffler, Dankward F. Struwe

Nuclear Technology / Volume 68 / Number 2 / February 1985 / Pages 180-225

Technical Paper / Fabrication of Components of the Creys-Malville Plant / Nuclear Safety / dx.doi.org/10.13182/NT85-A33554

Two Measures of Risk Importance and Their Application

William E. Vesely, Thomas C. Davis

Nuclear Technology / Volume 68 / Number 2 / February 1985 / Pages 226-234

Technical Paper / Fabrication of Components of the Creys-Malville Plant / Nuclear Safety / dx.doi.org/10.13182/NT85-A33555

The Fuel Cycle Effect of ²³⁶U in Pressurized Water Reactors

Ansar Parvez

Nuclear Technology / Volume 68 / Number 2 / February 1985 / Pages 235-241

Technical Paper / Fabrication of Components of the Creys-Malville Plant / Fuel Cycle / dx.doi.org/10.13182/NT85-A33556

Experimental and Analytical Study on the Time-Dependent Removal Efficiency of Methyl Iodide by an Impregnated Charcoal Bed

Soon Heung Chang, Won Jin Cho

Nuclear Technology / Volume 68 / Number 2 / February 1985 / Pages 242-251

Technical Paper / Fabrication of Components of the Creys-Malville Plant / Chemical Processing / dx.doi.org/10.13182/NT85-A33557

Considerations for Modeling Critical Heat Flux Behavior

Joe E. Dahlquist, Fred S. GL, Ralph A. Nelson

Nuclear Technology / Volume 68 / Number 2 / February 1985 / Pages 252-262

Technical Paper / Fabrication of Components of the Creys-Malville Plant / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33558

Reactor Physics Calculations on Close-Packed Pressurized Water Reactor Lattices

Erik Johansson

Nuclear Technology / Volume 68 / Number 2 / February 1985 / Pages 263-268

Technical Note / Fabrication of Components of the Creys-Malville Plant / Fission Reactor / dx.doi.org/10.13182/NT85-A33559

Number 3

Table of Contents
Authors(Ashwin P. Muzumdar, Douglas G. Andrews, Hsian Shi Tsai, P. Thomas, K. Nester, William E. Loewe, Hugues W. Bonin, Alexander Sesonske, O. K. Tallent, R. P. Wichner, Roy L. Towns, William J. Kovacs, Karl Bongartz, Dan T. Goodin, Graydon L. Yoder, Jr., David G. Morris, Charles B. Mullins, Gérard Ducros, Roland Gilbert, Lorenzo Ouellet, Yassin A. Hassan, J. H. Kim, Michio Murase, Hiroaki Suzuki, Ian J. Hastings, Elio Mizzan, John R. Kelm, Robert E. Moeller, J. Novak, Hans Rolf Käse, John Aloysius Tesk, Eldon Darrel Case)

A Semiempirical Relationship for the Excess Reactivity of a Reactor as a Function of Cycle Time, Axial Flux Form Factor, and Leakage Parameter

Ashwin P. Muzumdar, Douglas G. Andrews

Nuclear Technology / Volume 68 / Number 3 / March 1985 / Pages 275-280

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33574

Primary Coolant Feed and Bleed Operating Regions for the Midland Plant

Hsian Shi Tsai

Nuclear Technology / Volume 68 / Number 3 / March 1985 / Pages 281-292

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33575

Experimental Determination of the Atmospheric Dispersion Parameters at the Karlsruhe Nuclear Research Center for Emission Heights of 60 and 100 m

P. Thomas, K. Nester

Nuclear Technology / Volume 68 / Number 3 / March 1985 / Pages 293-310

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT85-A33576