Home / Publications / Journals / Nuclear Technology / Volume 55 / Number 2

Volume 55

Number 2

Table of Contents
Authors(C. N. Spalaris, P. J. Ring, E. A. Wright, J. Vrijen, J. K. van Westenbrugge, L. van der Wiel, P. L. F. Rademakers, C. P. Scheepens, J. W. Schinkel, Prodyot Roy, C. N. Spalaris, C. E. Sessions, S. D. Reynolds, Jr., M. A. Hebbar, J. F. Lewis, J. H. Kiefer, C. E. Sessions, C. F. Uber, G. R. Kirkland, E. R. Davies, M. E. Lambert, E. J. Kennett, A. A. Tavassoli, H. Touron, M. Weisz, H. J. Connors, D. S. Wood, J. L. Simpson, M. N. Robles, C. N. Spalaris, S. A. Moss, P. V. Balakrishnan, P. McSweeney, C. R. Frost, P. Walmsley, G. Van Drunen, V. S. Cecco, R. H. Renshaw, S. Roy, T. S. Bulischeck, D. van Rooyen, M. Kowaka, H. Nagano, T. Kudo, Y. Okada, M. Yagi, O. Takaba, T. Yonezawa, K. Arioka, C. R. Wolfe, J. N. Esposito, D. D. Whyte, J. M. Gilkison, J. R. Balavage, M. J. Wootten, S. M. Wozniak, R. H. Emanuelson, D. F. Levstek, K. E. Moore, G. J. Theus, G. P. Airey, A. R. Vaia, R. G. Aspden, P. Hurst, H. C. Cowen, Michael W. J. Lewis, Charles S. Campbell, G. R. Kirkland, E. R. Davies, M. E. Lambert, Kunihiko Satoh, Masao Toyoda, Shigetomo Matsui, Eisuke Mori, Shigeki Shimizu, Keisuke Satoh, S. G. Druce, B. C. Edwards, J. W. Martin, D. E. J. Talbot, B. Mukherjee, M. H. El Haddad, M. L. Vanderglas, D. V. Leemans, James Brown, Francisco Gonzalez, David Iley, Alexandra McKay, Brijesh Vyas, Carl J. Czajkowski, John R. Weeks)

Fabrication Technology—Liquid-Metal Fast Breeder Reactor Steam Generators

C. N. Spalaris, P. J. Ring, E. A. Wright

Nuclear Technology / Volume 55 / Number 2 / November 1981 / Pages 243-249

Technical Paper / Materials / dx.doi.org/10.13182/NT55-243

Material Selection and Optimization for Post-SNR-300 Steam Generators

J. Vrijen, J. K. van Westenbrugge, L. van der Wiel, P. L. F. Rademakers, C. P. Scheepens, J. W. Schinkel

Nuclear Technology / Volume 55 / Number 2 / November 1981 / Pages 250-258

Technical Paper / Materials / dx.doi.org/10.13182/NT55-250

Some Aspects of Materials Development for Sodium-Heated Steam Generators

Prodyot Roy, C. N. Spalaris

Nuclear Technology / Volume 55 / Number 2 / November 1981 / Pages 259-269

Technical Paper / Materials / dx.doi.org/10.13182/NT55-259

Materials Development for a Fast Breeder Reactor Steam Generator Concept

C. E. Sessions, S. D. Reynolds, Jr., M. A. Hebbar, J. F. Lewis, J. H. Kiefer

Nuclear Technology / Volume 55 / Number 2 / November 1981 / Pages 270-279

Technical Paper / Materials / dx.doi.org/10.13182/NT55-270

Steam Generator Tubing Development for Commercial Fast Breeder Reactors

C. E. Sessions, C. F. Uber

Nuclear Technology / Volume 55 / Number 2 / November 1981 / Pages 280-288

Technical Paper / Materials / dx.doi.org/10.13182/NT55-288

Metallurgical Examination of Tube-to-Tube-Plate Welds Removed from Dounreay Prototype Fast Reactor Evaporators

G. R. Kirkland, E. R. Davies, M. E. Lambert, E. J. Kennett

Nuclear Technology / Volume 55 / Number 2 / November 1981 / Pages 289-301

Technical Paper / Materials / dx.doi.org/10.13182/NT55-289

Effect of Decarburization on Structural and Mechanical Properties of Ferritic Steels

A. A. Tavassoli, H. Touron, M. Weisz

Nuclear Technology / Volume 55 / Number 2 / November 1981 / Pages 302-310

Technical Paper / Materials / dx.doi.org/10.13182/NT55-302

Flow-Induced Vibration and Wear of Steam Generator Tubes

H. J. Connors

Nuclear Technology / Volume 55 / Number 2 / November 1981 / Pages 311-331

Technical Paper / Materials / dx.doi.org/10.13182/NT55-311

Materials Property Requirements for Steam Generator Components in the Creep Range

D. S. Wood

Nuclear Technology / Volume 55 / Number 2 / November 1981 / Pages 332-338

Technical Paper / Materials / dx.doi.org/10.13182/NT55-332

Water Chemistry of Breeder Reactor Steam Generators

J. L. Simpson, M. N. Robles, C. N. Spalaris, S. A. Moss

Nuclear Technology / Volume 55 / Number 2 / November 1981 / Pages 339-348

Technical Paper / Materials / dx.doi.org/10.13182/NT55-339

A Chemical Cleaning Process for Nuclear Steam Generators

P. V. Balakrishnan, P. McSweeney, C. R. Frost, P. Walmsley

Nuclear Technology / Volume 55 / Number 2 / November 1981 / Pages 349-361

Technical Paper / Materials / dx.doi.org/10.13182/NT55-349

Eddy Current Inspection of a 17-Year-Old Nuclear Steam Generator

G. van Drunen, V. S. Cecco

Nuclear Technology / Volume 55 / Number 2 / November 1981 / Pages 362-370

Technical Paper / Materials / dx.doi.org/10.13182/NT55-362

Replacement of Damaged Steam Generator Tubing in 600-MW(electric) Canadian Deuterium Uranium Nuclear Plants

R. H. Renshaw, S. Roy

Nuclear Technology / Volume 55 / Number 2 / November 1981 / Pages 371-382

Technical Paper / Materials / dx.doi.org/10.13182/NT55-371

Effect of Environmental Variables on the Stress Corrosion Cracking of Inconel 600 Steam Generator Tubing

T. S. Bulischeck, D. van Rooyen

Nuclear Technology / Volume 55 / Number 2 / November 1981 / Pages 383-393

Technical Paper / Materials / dx.doi.org/10.13182/NT55-383

Effect of Heat Treatment on the Susceptibility to Stress Corrosion Cracking of Alloy 600

M. Kowaka, H. Nagano, T. Kudo, Y. Okada, M. Yagi, O. Takaba, T. Yonezawa, K. Arioka

Nuclear Technology / Volume 55 / Number 2 / November 1981 / Pages 394-404

Technical Paper / Materials / dx.doi.org/10.13182/NT55-394

Model Boiler Inhibition Studies of the Nuclear Steam Generator Denting Phenomenon

C. R. Wolfe, J. N. Esposito, D. D. Whyte, J. M. Gilkison, J. R. Balavage, M. J. Wootten, S. M. Wozniak

Nuclear Technology / Volume 55 / Number 2 / November 1981 / Pages 405-421

Technical Paper / Materials / dx.doi.org/10.13182/NT55-405

Materials Model Boiler Tests for the Babcock & Wilcox Once-Through Steam Generators

R. H. Emanuelson, D. F. Levstek, K. E. Moore, G. J. Theus

Nuclear Technology / Volume 55 / Number 2 / November 1981 / Pages 422-435

Technical Paper / Materials / dx.doi.org/10.13182/NT55-422

A Stress Corrosion Cracking Evaluation of Inconel 690 for Steam Generator Tubing Applications

G. P. Airey, A. R. Vaia, R. G. Aspden

Nuclear Technology / Volume 55 / Number 2 / November 1981 / Pages 436-448

Technical Paper / Materials / dx.doi.org/10.13182/NT55-436

The Stress Corrosion Cracking of 2 1/4 Cr—Mo Ferritic Steel in Caustic Environments

P. Hurst, H. C. Cowen

Nuclear Technology / Volume 55 / Number 2 / November 1981 / Pages 449-459

Technical Paper / Materials / dx.doi.org/10.13182/NT55-449

Fretting and Wear of Stainless and Ferritic Steels in Liquid-Metal Fast Breeder Reactor Steam Generators

Michael W. J. Lewis, Charles S. Campbell

Nuclear Technology / Volume 55 / Number 2 / November 1981 / Pages 460-469

Technical Paper / Materials / dx.doi.org/10.13182/NT55-460

Examination of Leaking Tube-to-Tube-Plate Welds from an Austenitic Steel Steam Generator Superheater in the Dounreay Prototype Fast Reactor

G. R. Kirkland, E. R. Davies, M. E. Lambert

Nuclear Technology / Volume 55 / Number 2 / November 1981 / Pages 470-478

Technical Paper / Materials / dx.doi.org/10.13182/NT55-478

Creep Behavior Evaluation of Hastelloy X Welded Joint

Kunihiko Satoh, Masao Toyoda, Shigetomo Matsui, Eisuke Mori, Shigeki Shimizu, Keisuke Satoh

Nuclear Technology / Volume 55 / Number 2 / November 1981 / Pages 479-486

Technical Paper / Materials / dx.doi.org/10.13182/NT55-479

On the Temper Embrittlement of Manganese-Molybdenum-Nickel Steels

S. G. Druce, B. C. Edwards

Nuclear Technology / Volume 55 / Number 2 / November 1981 / Pages 487-498

Technical Paper / Materials / dx.doi.org/10.13182/NT55-487

A Study of Crack Initiation in Corrosion Fatigue of AISI Type 316 Stainless Steel by Dynamic Measurement of Corrosion Current Transients

J. W. Martin, D. E. J. Talbot

Nuclear Technology / Volume 55 / Number 2 / November 1981 / Pages 499-504

Technical Paper / Materials / dx.doi.org/10.13182/NT55-504

Low Cycle Fatigue of Steam Generator Tubes in the Vicinity of Roll Joints

B. Mukherjee, M. H. El Haddad, M. L. Vanderglas, D. V. Leemans

Nuclear Technology / Volume 55 / Number 2 / November 1981 / Pages 505-512

Technical Paper / Materials / dx.doi.org/10.13182/NT55-505

Studies of Denting of Steam Generators with Simulated Fresh Water In-Leakage

James Brown, Francisco Gonzalez, David Iley, Alexandra McKay

Nuclear Technology / Volume 55 / Number 2 / November 1981 / Pages 513-524

Technical Paper / Materials / dx.doi.org/10.13182/NT55-513

Metallurgical Examination of Cracked Feedwater Pipes from Nine Pressurized Water Reactors

Brijesh Vyas, Carl J. Czajkowski, John R. Weeks

Nuclear Technology / Volume 55 / Number 2 / November 1981 / Pages 525-537

Technical Paper / Materials / dx.doi.org/10.13182/NT55-525