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Volume 46

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Common-Mode Failures in Redundancy Systems

I. A. Watson, G. T. Edwards

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

December 1979

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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 / Pages 192-198

December 1979

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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 / Pages 199-204

December 1979

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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 / Pages 205-212

December 1979

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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 / Pages 213-219

December 1979

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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 / Pages 220-227

December 1979

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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 / Pages 228-233

December 1979

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

H. Kwast

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

December 1979

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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 / Pages 241-247

December 1979

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

K. Schwarzer

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

December 1979

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Chemical Reactions Between Light Water Reactor Core Melt and Concrete

Alfred Skokan, Helmut Holleck, Martin Peehs

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

December 1979

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Modeling of Equiaxed Grain Growth in Uranium Dioxide Fuels

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

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

December 1979

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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 / Pages 268-280

December 1979

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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 / Pages 281-288

December 1979

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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 / Pages 289-299

December 1979

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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 / Pages 300-305

December 1979

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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 / Pages 306-311

December 1979

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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 / Pages 312-317

December 1979

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Controlling Cesium in the Coolant of the Experimental Breeder Reactor II

W. H. Olson, W. E. Ruther

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

December 1979

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A Revised ANS Standard for Decay Heat from Fission Products

Virgil E. Schrock

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

December 1979

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