Home / Publications / Journals / Nuclear Technology / Volume 46 / Number 3

Volume 46

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