Home / Publications / Journals / Nuclear Technology / Volume 46 / Number 2

Volume 46

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