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Volume 69

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Number 1

Table of Contents
Authors(Yaakov Lugasi, Abraham Mehrez, Zilla Sinuany-Stern, Gary Chung, Nathan Siu, George Apostolakis, Mohammad Modarres, Theodore W. Cadman, Erasmia Lois, Alan R. Gardner, Marcel Y. Ballinger, Peter C. Owczarski, Werner Heit, Hans Huschka, Wilhelm Rind, Günter G. Kaiser, Robert E. Einziger, James A. Cook, Gottfried Class, Klaus Hain, Rainer Meyder, David G. Morris, Charles B. Mullins, Graydon L. Yoder, Jr., V. K. (Bindi) Chexal, Jason Chao, Robert E. Nickell, Timothy J. Griesbach, U. S. Rohatgi, Mineo Mizuno, Yuji Enokido, Ichiro Unno, Keiichi Kono, Sadamu Yamanouchi, Toshiyuki Itaki, B. P. McGrail, L. A. Chick, G. L. McVay)
Equity Issues in Radioactive Waste Management(Donald A. Daavettila)
Iodine-129: Evaluation of Releases from Nuclear Power Generation(Geoffrey G. Eichholz)
Computational Methods for Turbulent, Transonic and Viscous Flows(Efstathios E. Michaelides)
Social and Economic Aspects of Radioactive Waste Disposal: Considerations for Institutional Management(Raymond L. Murray)

Nuclear Power Plant Site Selection: A Case Study

Yaakoy Lugasi, Abraham Mehrez, Zilla Sinuany-Stern

Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 7-13

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT85-A33590

Improvements in Compartment Fire Modeling and Simulation of Experiments

Gary Chung, Nathan Siu, George Apostolakis

Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 14-26

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT85-A33591

Sensitivity and Uncertainty Analyses for the Accident Sequence Precursor Study

Mohammad Modarres, Theodore W. Cadman, Erasmia Lois, Alan R. Gardner

Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 27-35

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT85-A33592

Radioactive Source Term Models in a Compartment Fire Code

Marcel Y. Ballinger, Peter C. Owczarski

Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 36-43

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT85-A33593

Status of Qualification of High-Temperature Reactor Fuel Element Spheres

Werner Heit, Hans Huschka, Wilhelm Rind, Günter G. Kaiser

Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 44-54

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT85-A33594

Behavior of Breached Light Water Reactor Spent Fuel Rods in Air and Inert Atmospheres at 229°C

Robert E. Einziger, James A. Cook

Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 55-71

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT85-A33595

Measurement of Cladding Temperatures with Loss-of-Fluid-Test Thermocouples in the COSIMA Blowdown Test Facility

Gottfried Class, Klaus Hain, Rainer Meyder

Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 72-81

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33596

An Experimental Study of Rod Bundle Dispersed-Flow Film Boiling with High-Pressure Water

David G. Morris, Charles B. Mullins, Graydon L. Yoder, Jr.

Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 82-93

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33597

An Empirical Mixing Model for Pressurized Thermal Shock Applications

V. K. (Bindi) Chexal, Jason Chao, Robert E. Nickell, Timothy J. Griesbach

Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 94-99

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33598

Assessment of TRAC Codes with Dartmouth College Countercurrent Flow Tests

U. S. Rohatgi

Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 100-106

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33599

Development of a New Measurement Method for Fast Breeder Reactor Fuel Burnup Using a Shielded lon Microprobe Analyzer

Mineo Mizuno, Yuji Enokido, Ichiro Unno, Keiichi Kono, Sadamu Yamanouchi, Toshiyuki Itaki

Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 107-113

Technical Paper / Technique / dx.doi.org/10.13182/NT85-A33600

Initial Results for the Experimental Evaluation of a Nuclear Waste Repository Source Term Model

B. P. McGrail, L. A. Chick, G. L. McVay

Nuclear Technology / Volume 69 / Number 1 / April 1985 / Pages 114-118

Technical Note / Radioactive Waste Management / dx.doi.org/10.13182/NT85-A33601

Number 2

Table of Contents
Authors(Edward T. Dugan, Nils J. Diaz, Edward E. Carroll, Jr., H. M. Forehand, E. Dow Whitney, Dae Joon Kim, Dennis S. Tucker, Calvin C. Oliver, Edward T. Dugan, Hans S. Häggblom, Werner Faubel, Sameh A. Ali, R. Kohli, D. Stahl, V. Pasupathi, A. B. Johnson, Jr., E. R. Gilbert, Richard W. Smith, Gary S. Was, Yasunori Bessho, Sadao Uchikawa, Clarence E. Lee, Joe W. Durkee, H. Mogard, H. Knaab, U. Bergenlid, G. Lysell)
Preface: Gaseous Core Reactors(Nils J. Diaz)

Gas Core Reactor Neutronics —Theoretical Modeling and Experimental Verification

Edward T. Dugan, Nils J. Diaz, Edward E. Carroll, Jr., H. M. Forehand

Nuclear Technology / Volume 69 / Number 2 / May 1985 / Pages 134-153

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33625

A Study of Corrosion-Resistant Materials for Pulsed Gaseous Core Nuclear Systems

E. Dow Whitney, Dae Joon Kim, Dennis S. Tucker+

Nuclear Technology / Volume 69 / Number 2 / May 1985 / Pages 154-160

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33626

Thermophysical Properties of UF₆-He Mixtures Relevant to Circulating Gas Core Reactor Systems

Calvin C. Oliver, Edward T. Dugan

Nuclear Technology / Volume 69 / Number 2 / May 1985 / Pages 161-169

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33627

Transfer of Molecular Fission Products Between a Gas and a Surface, with Application to Iodine Retention in a Granular Bed

Hans S. Häggblom

Nuclear Technology / Volume 69 / Number 2 / May 1985 / Pages 170-177

Nuclear Safety / dx.doi.org/10.13182/NT85-A33628

Decontamination of Carbonate Containing Process Streams in Nuclear Fuel Reprocessing by Ion Exchange Chromatography

Werner Faubel, Sameh A. AL

Nuclear Technology / Volume 69 / Number 2 / May 1985 / Pages 178-185

Chemical Processing / dx.doi.org/10.13182/NT85-A33629

The Behavior of Breached Boiling Water Reactor Fuel Rods on Long-Term Exposure to Air and Argon at 598 K

R. Kohli, D. Stahl, V. Pasupathi, A. B. Johnson, Jr., E. R. Gilbert

Nuclear Technology / Volume 69 / Number 2 / May 1985 / Pages 186-197

Nuclear Fuel / dx.doi.org/10.13182/NT85-A33630

FCODE-BETA/SS: A Fuel Performance Code for Stainless Steel Clad Pressurized Water Reactor Fuel

Richard W. Smith, Gary S. Was

Nuclear Technology / Volume 69 / Number 2 / May 1985 / Pages 198-209

Nuclear Fuel / dx.doi.org/10.13182/NT85-A33631

Subchannel Analysis Program for Boiling Water Reactor Fuel Bundles Based on Five Conservation Equations of Two-Phase Flow

Yasunori Bessho, Sadao Uchikawa

Nuclear Technology / Volume 69 / Number 2 / May 1985 / Pages 210-217

Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33632

Multiregion Concentration Diffusion Coefficient Determination Using Davidon’s Variable Metric Method

Clarence E. Lee, Joe W. Durkee

Nuclear Technology / Volume 69 / Number 2 / May 1985 / Pages 218-235

Analyse / dx.doi.org/10.13182/NT85-A33633

The International DEMO-RAMP-II Project at Studsvik

H. Mogard, H. Knaab, U. Bergenlid, G. Lysell

Nuclear Technology / Volume 69 / Number 2 / May 1985 / Pages 236-242

Technical Note / Nuclear Fuel / dx.doi.org/10.13182/NT85-A33634

Number 3

Table of Contents
Authors(M. J. Hazzan, M. S. Stocknoff, David W. Barcomb, Timothy Irving, Yassin A. Hassan, H. S. Kim, S. I. Abdel-Khalik, Douglas J . Rzepecki, Tawfik A. Al-Kusayer, V. F. Baston, K. J. Hofstetter, A. P. Malinauskas, Ronald F. Tuttle, Sudarshan K. Loyalka, Carol Ahnert, José M. Aragonés, Kousaku Fukuda, Ekkehard Groos, John Rau, Jess M. Cleveland, Terry F. Rees, Kenneth L. Nash, Yassin A. Hassan, John W. Wilson, Govind S. Khandelwal)

Radiation Levels During Shutdown in Boiling Water Reactors

M. J. Hazzan, M. S. Stocknoff, David W. Barcomb, Timothy Irving

Nuclear Technology / Volume 69 / Number 3 / June 1985 / Pages 249-256

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33608

Three-Dimensional Calculations of Fluid-Thermal Mixing in a Babcock & Wilcox Plant at Stagnated Loop Flow

Yassin A. Hassan

Nuclear Technology / Volume 69 / Number 3 / June 1985 / Pages 257-267

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33609

Convective Cooling of Simulated Core Debris Beds

H. S. Kim, S. I. Abdel-Khalik

Nuclear Technology / Volume 69 / Number 3 / June 1985 / Pages 268-278

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT85-A33610