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Volume 46

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Number 1

Table of Contents
Authors(Y. Naito, M. Mimura, M. Toba, R. Onuki, John R. Phillips, Barry K. Barnes, Thomas R. Bement, J. R. Engel, W. A. Rhoades, W. R. Grimes, J. F. Dearing, Jim P. Wei, Yigal Ronen, Jeffrey N. Brooks, Robert L. Kustom, D. R. Harris, M. Becker, A. Parvez, J. M. Ryskamp, Bruce W. Moran, J. D. Navratil, L. L. Martella, Shan Heng Chien, A. R. Wazzan, D. Okrent, T. P. Toepker, J. N. Anno, L. C. Walters, C. M. Walter, James F. Davis, Richard S. H. Mah, William F. Stevens, Balabhadra Misra, Victor A. Maroni, R. W. Terhune, H. D. Glenn, D. E. Burton, H. L. McKague, J. T. Rambo)
Nuclear Power Reactor Safety(Reiner Papp)

A New Expression of Few-Group Nuclear Constants for Analyzing Light Water Reactor Cores

Y. Naito, M. Mimura, M. Toba, R. Onuki

Nuclear Technology / Volume 46 / Number 1 / November 1979 / Pages 7-20

Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32375

Correlation of the Cesium-134/Cesium-137 Ratio to Fast Reactor Burnup

John R. Phillips, Barry K. Barnes, Thomas R. Bement

Nuclear Technology / Volume 46 / Number 1 / November 1979 / Pages 21-29

Technical Paper / Reactor / dx.doi.org/10.13182/NT46-21

Molten-Salt Reactors for Efficient Nuclear Fuel Utilization Without Plutonium Separation

J. R. Engel, W. A. Rhoades, W. R. Grimes, J. F. Dearing

Nuclear Technology / Volume 46 / Number 1 / November 1979 / Pages 30-43

Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32377

A Simplified Interassembly Heat Transfer Model for the Analysis of Liquid-Metal Fast Breeder Reactor Core Restraint Systems

Jim P. Wei

Nuclear Technology / Volume 46 / Number 1 / November 1979 / Pages 44-52

Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32378

A Method for Refueling Light Water Reactors with Natural Uranium

Yigal Ronen

Nuclear Technology / Volume 46 / Number 1 / November 1979 / Pages 53-60

Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32379

Power Supply Requirements for a Tokamak Fusion Reactor

Jeffrey N. Brooks, Robert L. Kustom

Nuclear Technology / Volume 46 / Number 1 / November 1979 / Pages 61-81

Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32380

Sensitivity of Nuclear Fuel Cycle Cost to Uncertainties in Nuclear Data

Nuclear Technology / Volume 46 / Number 1 / November 1979 / Pages 82-97

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT79-A32381

An Automated Gravimetric Titrator for the Determination of Uranium in Safeguards Materials

Bruce W. Moran

Nuclear Technology / Volume 46 / Number 1 / November 1979 / Pages 98-104

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT79-A32382

Comparison of Anion Exchange Resins for Recovering Plutonium from Nitric Acid Waste

J. D. Navratil, L. L. Martella

Nuclear Technology / Volume 46 / Number 1 / November 1979 / Pages 105-109

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT79-A32383

The Effect of Solid Fission Products and Dislocations on Oxide Fuel Element Behavior in Fast Overpower Transients

Shan Heng Chien, A. R. Wazzan, D. Okrent

Nuclear Technology / Volume 46 / Number 1 / November 1979 / Pages 110-126

Technical Paper / Fuel / dx.doi.org/10.13182/NT79-A32384

Radiation-Induced Outgassing from Type 304 Stainless Steel

T. P. Toepker, J. N. Anno

Nuclear Technology / Volume 46 / Number 1 / November 1979 / Pages 127-133

Technical Paper / Material / dx.doi.org/10.13182/NT79-A32385

Observations of Dilation and Bowing in Experimental Breeder Reactor II Ducts and Cladding

L. C. Walters, C. M. Walter

Nuclear Technology / Volume 46 / Number 1 / November 1979 / Pages 134-148

Technical Paper / Material / dx.doi.org/10.13182/NT79-A32386

Dynamics and Control of a Packed Distillation Column for the Isotopic Enrichment of Plasma Exhausts from Controlled Thermonuclear Reactors

James F. Davis, Richard S. H. Mah, William F. Stevens, Balabhadra Misra, Victor A. Maroni

Nuclear Technology / Volume 46 / Number 1 / November 1979 / Pages 149-158

Technical Paper / ISotopes Separation / dx.doi.org/10.13182/NT79-A32387

Numerical Simulation of the Baneberry Event

R. W. Terhune, H. D. Glenn, D. E. Burton, H. L. McKague, J. T. Rambo

Nuclear Technology / Volume 46 / Number 1 / November 1979 / Pages 159-169

Technical Paper / Nuclear Explosive / dx.doi.org/10.13182/NT79-A32388

Number 2

Table of Contents
Authors(I. A. Watson, G. T. Edwards, Martin Peehs, Alfred Skokan, M. Reimann, Yi-Shung Chen, William S. Haigh, L. Harold Sullivan, Stewart R. Fischer, B. Brzoska, F. Depisch, H. P. Fuchs, W. Sauermann, Dennis R. Coleman, K. M. Rose, C. A. Mann, E. D. Hindle, W. Schenk, A. Naoumidis, H. Kwast, Helmut Peter Thomas, K. Schwarzer, Alfred Skokan, Helmut Holleck, Martin Peehs, William L. Baldewicz, Ahmed R. Wazzan, David Okrent, W. T. Sha, H. M. Domanus, R. C. Schmitt, J. J. Oras, E. I. H. Lin, V. L. Shah, W. Kramer, K. Schleisiek, L. Schmidt, G. Vanmassenhove, A. Verwimp, R. Nijsing, W. Eifler, Siegfried Vogt, Wolfgang G. Hübschmann, K. Petersen, H. Barthels, H. E. Drescher, C. B. von der Decken, N. Iniotakis, W. Schenk, R. Schulten, W. Steinwarz, H. J. Cordewiner, H. D. Röhrig, W. H. Olson, W. E. Ruther, Virgil E. Schrock, H. A. Morewitz, R. P. Johnson, C T. Nelson, E. U. Vaughan, C. A. Guderjahn, R. K. Hilliard, J. D. McCormack, A. K. Postma, Samuel A. Naff, William F. Schwarz, J. B. Rivard, Herbert J. Sutherland, Vijay K. Dhir, Ivan Catton, Kent Mehr, Heinz M. Kottowski, Horst Goldammer, Vladislav Adamík)

Common-Mode Failures in Redundancy Systems

I. A. Watson, G. T. Edwards

Nuclear Technology / Volume 46 / Number 2 / December 1979 / Pages 183-191

Technical Paper / Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor / dx.doi.org/10.13182/NT79-A32315

The Behavior of Concrete in Contact with Molten Corium in the Case of a Hypothetical Core Melt Accident

Martin Peehs, Alfred Skokan, M. Reimann

Nuclear Technology / Volume 46 / Number 2 / December 1979 / Pages 192-198

Technical Paper / Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor / dx.doi.org/10.13182/NT46-192

Test Prediction for the German PKL Test K5A Using RELAP4/MOD6

Yi-Shung Chen, William S. Haigh, L. Harold Sullivan, Stewart R. Fischer

Nuclear Technology / Volume 46 / Number 2 / December 1979 / Pages 199-204

Technical Paper / Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor / dx.doi.org/10.13182/NT79-A32317

Parameter Study on the Influence of Prepressurization on PWR Fuel Rod Behavior During Normal Operation and Hypothetical LOCAs

B. Brzoska, F. Depisch, H. P. Fuchs, W. Sauermann

Nuclear Technology / Volume 46 / Number 2 / December 1979 / Pages 205-212

Technical Paper / Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor / dx.doi.org/10.13182/NT79-A32318

Comparisons Between Measured and FRAP-T4-Predicted Fuel Rod Failure Probability Under Pellet-Cladding Interaction Conditions

Dennis R. Coleman

Nuclear Technology / Volume 46 / Number 2 / December 1979 / Pages 213-219

Technical Paper / Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor / dx.doi.org/10.13182/NT79-A32319

The Axial Distribution of Deformation in the Cladding of Pressurized Water Reactor Fuel Rods in a Loss-of-Coolant Accident

K. M. Rose, C. A. Mann, E. D. Hindle

Nuclear Technology / Volume 46 / Number 2 / December 1979 / Pages 220-227

Technical Paper / Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor / dx.doi.org/10.13182/NT79-A32320

Failure Mechanisms and Fission Product Release in High-Temperature Gas-Cooled Reactor Fuel Under Conditions of Unrestricted Core Heatup Events

W. Schenk, A. Naoumidis

Nuclear Technology / Volume 46 / Number 2 / December 1979 / Pages 228-233

Technical Paper / Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor / dx.doi.org/10.13182/NT79-A32321

Modes of Failure of Fast Reactor Fuel Pins Irradiated Under Loss-of-Coolant-Flow Conditions

H. Kwast

Nuclear Technology / Volume 46 / Number 2 / December 1979 / Pages 234-240

Technical Paper / Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor / dx.doi.org/10.13182/NT79-A32322

An On-Line Meteorological Information System for Response to Accidental Releases of Radioactivity into the Atmosphere

Helmut Peter Thomas

Nuclear Technology / Volume 46 / Number 2 / December 1979 / Pages 241-247

Technical Paper / Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor / dx.doi.org/10.13182/NT79-A32323

Radionuclide Transport in Soil—Description and Application of a Calculational Model

K. Schwarzer

Nuclear Technology / Volume 46 / Number 2 / December 1979 / Pages 248-254

Technical Paper / Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor / dx.doi.org/10.13182/NT79-A32324

Chemical Reactions Between Light Water Reactor Core Melt and Concrete

Alfred Skokan, Helmut Holleck, Martin Peehs

Nuclear Technology / Volume 46 / Number 2 / December 1979 / Pages 255-262

Technical Paper / Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor / dx.doi.org/10.13182/NT79-A32325

Modeling of Equiaxed Grain Growth in Uranium Dioxide Fuels

William L. Baldewicz, Ahmed R. Wazzan, David Okrent

Nuclear Technology / Volume 46 / Number 2 / December 1979 / Pages 263-267

Technical Paper / Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor / dx.doi.org/10.13182/NT79-A32326

A New Approach for Rod-Bundle Thermal-Hydraulic Analysis

W. T. Sha, H. M. Domanus, R. C. Schmitt, J. J. Oras, E. I. H. Lin, V. L. Shah

Nuclear Technology / Volume 46 / Number 2 / December 1979 / Pages 268-280

Technical Paper / Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor / dx.doi.org/10.13182/NT79-A32327

Investigation of Local Cooling Disturbances in an In-Pile Sodium Loop in the BR2

W. Kramer, K. Schleisiek, L. Schmidt, G. Vanmassenhove, A. Verwimp

Nuclear Technology / Volume 46 / Number 2 / December 1979 / Pages 281-288

Technical Paper / Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor / dx.doi.org/10.13182/NT79-A32328

Considerations on Incoherency of Boiling and Voiding in Liquid-Metal Fast Breeder Reactor Subassemblies During a Loss-of-Flow Accident

R. Nijsing, W. Eifler

Nuclear Technology / Volume 46 / Number 2 / December 1979 / Pages 289-299

Technical Paper / Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor / dx.doi.org/10.13182/NT79-A32329

The Influence of Meteorological Parameters on the Consequences of Accidental Activity Releases from Nuclear Power Plants

Siegfried Vogt, Wolfgang G. Hübschmann

Nuclear Technology / Volume 46 / Number 2 / December 1979 / Pages 300-305

Technical Paper / Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor / dx.doi.org/10.13182/NT79-A32330

The Fission Product Retention of Pebble-Bed Reactors in Ultimate Accidents

K. Petersen, H. Barthels, H. E. Drescher, C. B. Von Der Decken, N. Iniotakis, W. Schenk, R. Schulten

Nuclear Technology / Volume 46 / Number 2 / December 1979 / Pages 306-311

Technical Paper / Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor / dx.doi.org/10.13182/NT79-A32331

Tritium Contamination of the Product Gas in a High-Temperature Reactor Heated Process Plant

W. Steinwarz, H. J. Cordewiner, H. D. Röhrig

Nuclear Technology / Volume 46 / Number 2 / December 1979 / Pages 312-317

Technical Paper / Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor / dx.doi.org/10.13182/NT79-A32332

Controlling Cesium in the Coolant of the Experimental Breeder Reactor II

W. H. Olson, W. E. Ruther

Nuclear Technology / Volume 46 / Number 2 / December 1979 / Pages 318-322

Technical Paper / Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor / dx.doi.org/10.13182/NT79-A32333

A Revised ANS Standard for Decay Heat from Fission Products

Virgil E. Schrock

Nuclear Technology / Volume 46 / Number 2 / December 1979 / Pages 323-331

Technical Paper / Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor / dx.doi.org/10.13182/NT79-A32334

Attenuation of Airborne Debris from Liquid-Metal Fast Breeder Reactor Accidents

H. A. Morewitz, R. P. Johnson, C. T. Nelson, E. U. Vaughan, C. A. Guderjahn, R. K. Hilliard, J. D. McCormack, A. K. Postma

Nuclear Technology / Volume 46 / Number 2 / December 1979 / Pages 332-339

Technical Paper / Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor / dx.doi.org/10.13182/NT79-A32335

Steam-Water Mixing in Nuclear Reactor Safety Loss-of-Coolant Experiments

Samuel A. Naff, William F. Schwarz

Nuclear Technology / Volume 46 / Number 2 / December 1979 / Pages 340-343

Technical Paper / Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor / dx.doi.org/10.13182/NT79-A32336

In-Reactor Experiments on the Cooling of Fast Reactor Debris

J. B. Rivard

Nuclear Technology / Volume 46 / Number 2 / December 1979 / Pages 344-349

Technical Paper / Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor / dx.doi.org/10.13182/NT79-A32337

Acoustic Measurement of the Penetration of a Molten Metallic Pool into Concrete

Herbert J. Sutherland

Nuclear Technology / Volume 46 / Number 2 / December 1979 / Pages 350-355

Technical Paper / Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor / dx.doi.org/10.13182/NT79-A32338

Dryout Heat Fluxes in Debris Beds Cooled at the Bottom and Having Subcooled Liquid at the Top

Vijay K. Dhir, Ivan Catton

Nuclear Technology / Volume 46 / Number 2 / December 1979 / Pages 356-361

Technical Paper / Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor / dx.doi.org/10.13182/NT79-A32339

Multichannel Model for Fuel-Coolant Interaction in a Liquid-Metal Fast Breeder Reactor Subassembly

Kent Mehr, Heinz M. Kottowski, Horst Goldammer

Nuclear Technology / Volume 46 / Number 2 / December 1979 / Pages 362-368

Technical Paper / Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor / dx.doi.org/10.13182/NT79-A32340

A Theoretical Study of Reinforced Concrete Structures Under Missile Impact Loading

Vladislav Adamík

Nuclear Technology / Volume 46 / Number 2 / December 1979 / Pages 369-377

Technical Paper / Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor / dx.doi.org/10.13182/NT79-A32341

Number 3

Table of Contents
Authors(T. Ginsberg, O. C. Jones, Jr., J. C. Chen, H. Deuber, J. G. Wilhelm, R. A. Lorenz, J. L. Collins, A. P. Malinauskas, J. J. Pyun, K. A. Williams, Charles E. Cartmill, Jorma Arros, J. H. Pitts, E. W. McCauley, R. E. Leadon, N. A. Lurie, V. K. Dhir, W. E. Kastenberg, D. W. Varela, A. Renard, G. Evrard, U. Wehmann, Robert P. Wadkins, Richard G. Ambrosek, Michael W. Young, Hsu-Chieh Yeh, Cleon E. Dodge, Lawrence E. Hochreiter, A. Segev, R. E. Henry, S. G. Bankoff, David J. Diamond, Hsiang-Shou Cheng, Cl. Vandenberg, H. Bonet, A. Charlier, F. Motte, J. C. Luxat, G.M. Frescura, S. K. Bhattacharyya, D. C. Wade, R. G. Bucher, D. M. Smith, R. D. McKnight, L. G. LeSage, W. P. Barthold, J. C. Beitel, P. S. K. Lam, Y. Orechwa, S. F. Su, R. B. Turski, G. Enderle, F. Katz, H. Mösinger, E. G. Schlechtendahl, K. Stölting, D. J. Kowalski, V. J. Esposito, J. Y. Boivin, H. Karwat, H. Albrecht, V. Matschoss, H. Wild, A. J. Buslik, R. E. Hall, Gérard Kurka, Alain Harrer, Pierre Chenebault, J. L. Quinet, L. Lannou, N. P. Wilburn, D. E. Smith, R. E. Baars, D. B. Atcheson, B. W. Spencer, Peter K. Mast, James H. Scott, L. Mergan, J. Storrer, R. Verbeke, J. P. Cordier)

Flow Behavior of Volume-Heated Boiling Pools: Implications with Respect to Transition Phase Accident Conditions

T. Ginsberg, O. C. Jones, Jr., J. C. Chen

Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 391-398

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32344

Determination of the Sources of the Airborne Physico-Chemical Iodine-131 Species in a Pressurized Water Reactor Power Plant

H. Deuber, J. G. Wilhelm

Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 399-403

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32345

Fission Product Source Terms for the Light Water Reactor Loss-of-Coolant Accident

R. A. Lorenz, J. L. Collins, A. P. Malinauskas

Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 404-410

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32346

TRAC Analysis of Loss-of-Fluid Test Non-Nuclear Test L1-4

J. J. Pyun, K. A. Williams

Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 411-421

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32347

Analysis of a Simulated Small Break in the Semiscale System Under Loss-of-Coolant Accident Conditions

Charles E. Cartmill

Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 422-427

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32348

Coupled Vibrations of a Structure and Fluid Excited by Pressure Shocks

Jorma Arros

Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 428-432

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32349

Vent Clearing During a Simulated Loss-of-Coolant Accident in a Mark I Boiling Water Reactor Pressure-Suppression System

J. H. Pitts, E. W. McCauley

Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 433-441

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32350

Damage Mechanisms to Cables in Reactor Loss-of-Coolant Accident Environments

R. E. Leadon, N. A. Lurie

Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 442-446

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32351

Thermal-Hydraulic Analysis of Fuel Blockages Formed During Transient Overpower Accidents in Liquid-Metal Fast Breeder Reactors

V. K. Dhir, W. E. Kastenberg, D. W. Varela

Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 447-452

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32352

Comparative Study of Heterogeneous and Homogeneous Liquid-Metal Fast Breeder Reactor Cores in Some Accident Conditions

A. Renard, G. Evrard, U. Wehmann

Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 453-464

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32353

Rod Bundle Critical Heat Flux at Low Pressure

Robert P. Wadkins, Richard G. Ambrosek, Michael W. Young

Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 465-472

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32354

Reflood Heat Transfer Correlation

Hsu-Chieh Yeh, Cleon E. Dodge, Lawrence E. Hochreiter

Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 473-481

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32355

Fuel-Coolant Interactions in a Shock Tube Geometry

A. Segev, R. E. Henry, S. G. Bankoff

Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 482-492

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32356

Higher Order Effects in Calculating Boiling Water Reactor Doppler and Void Reactivity Feedback

David J. Diamond, Hsiang-Shou Cheng

Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 493-499

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32357

Safety Aspects of Using Gadolinium as Burnable Poison in Pressurized Water Reactors

Cl. Vandenberg, H. Bonet, A. Charlier, F. Motte

Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 500-506

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32358

Space-Time Neutronic Analysis of Postulated Loss-of-Coolant Accidents in CANDU Reactors

J. C. Luxat, G. M. Frescura

Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 507-516

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32359

A Critical Experimental Study of Integral Physics Parameters in Simulated Liquid-Metal Fast Breeder Reactor Meltdown Cores

S. K. Bhattacharyya, D. C. Wade, R. G. Bucher, D. M. Smith, R. D. McKnight, L. G. LeSage

Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 517-524

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32360

Low Sodium Void Cores

W. P. Barthold, J. C. Beitel, P. S. K. Lam, Y. Orechwa, S. F. Su, R. B. Turski

Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 525-528

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32361

Pressure Field and Core Barrel Loadings During Pressurized Water Reactor Blowdown

G. Enderle, F. Katz, H. Mösinger, E. G. Schlechtendahl, K. Stölting

Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 529-535

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32362

Application of Fluid-Structure Interaction for Steam Generator Force Analysis

D. J. Kowalski, V. J. Esposito

Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 536-539

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32363

Two-Phase Critical Flow in Long Nozzles

J. Y. Boivin

Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 540-545

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32364

Analytical Simulations in the Field of Two-Phase Flow: A Promising Scaling Law for the Interpretation of Experiments

H. Karwat

Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 546-558

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32365

Release of Fission and Activation Products During Light Water Reactor Core Meltdown

H. Albrecht, V. Matschoss, H. Wild

Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 559-565

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32366

Radioactivity Release Versus Probability for a Steam Generator Tube Rupture Accident

A. J. Buslik, R. E. Hall

Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 566-570

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32367

Fission Product Release from a Pressurized Water Reactor Defective Fuel Rod: Effect of Thermal Cycling

Gerard Kurka, Alain Harrer, Pierre Chenebault

Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 571-581

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32368

LMFBR Steam Generators: Behavior of Heat Exchange Tubes Faced with a Through Crack Resulting in Contact Between Sodium and Water

J. L. Quinet, L. Lannou

Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 582-590

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32369

Fuel Pins and Core Response Under Liquid-Metal Fast Breeder Reactor Transient Overpower Accident Conditions

N. P. Wilburn, D. E. Smith, R. E. Baars, D. B. Atcheson,, B. W. Spencer

Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 591-599

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32370

An Analysis of Transient Overpower Accidents in the Fast Test Reactor Using the Los Alamos Failure Model

Peter K. Mast, James H. Scott

Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 600-605

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32371

Safety Aspects of Light Water Reactor Radwaste Solidification Processes

L. Mergan, J. Storrer, R. Verbeke, J. P. Cordier

Nuclear Technology / Volume 46 / Number 3 / December 1979 / Pages 606-610

Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT79-A32372