Home / Publications / Journals / Nuclear Technology / Volume 55

Volume 55

Number 1 | Number 2 | Number 3

Number 1

Table of Contents
Authors(Stanley J. Green, J. Peter N. Paine, G. F. Taylor, D. P. Dautovich, J. E. Chafey, D. I. Roberts, D. W. James, C. C. Stone, J. A. Ford, F. E. Tippets, J. S. McDonald, G. Grant, J. L. Epstein, Ph. Berge, J. R. Donati, Paul Cohen, Frederick J. Pocock, R. Garnsey, D. J. Parry, Earl L. White, Warren E. Berry, P. J. Cameron, J. Walters, K. Ohnishi, H. Tsukada, M. Kusuhashi, Y. Tanaka, R. S. Pathania, E. G. McVey, Martin W. Kendig, Hugh S. Isaacs, P. J. King, D. P. Dautovich, C. R. Frost, P. Walmsley, P. V. Balakrishnan, P. McSweeney, M. H. Knaap, H. C. D. Nieuwland, J. Vrijen, J. K. van Westenbrugge, W. Husslage, C. P. Scheepens, J. W. Schinkel)

Materials Performance In Nuclear Pressurized Water Reactor Steam Generators

Stanley J. Green, J. Peter N. Paine

Nuclear Technology / Volume 55 / Number 1 / October 1981 / Pages 10-29

Technical Paper / Materials Performance in Nuclear Steam Generator / Material / dx.doi.org/10.13182/NT81-A32828

Materials Performance in CANDU Nuclear Steam Generators

G. F. Taylor, D. P. Dautovich

Nuclear Technology / Volume 55 / Number 1 / October 1981 / Pages 30-36

Technical Paper / Materials Performance in Nuclear Steam Generator / Material / dx.doi.org/10.13182/NT81-A32829

Steam Generator Materials Performance in High Temperature Gas-Cooled Reactors

J. E. Chafey, D. I. Roberts

Nuclear Technology / Volume 55 / Number 1 / October 1981 / Pages 37-49

Technical Paper / Materials Performance in Nuclear Steam Generator / Material / dx.doi.org/10.13182/NT81-A32830

Experience In Operating Gas-Cooled Reactor Steam Generators of U.K. Design

D. W. James

Nuclear Technology / Volume 55 / Number 1 / October 1981 / Pages 50-59

Technical Paper / Materials Performance in Nuclear Steam Generator / Material / dx.doi.org/10.13182/NT81-A32831

Experience with Liquid-Metal Fast Breeder Reactor Steam Generators-U.S. Design

C. C. Stone, J. A. Ford, F. E. Tippets, J. S. McDonald, G. Grant, J. L. Epstein

Nuclear Technology / Volume 55 / Number 1 / October 1981 / Pages 60-87

Technical Paper / Materials Performance in Nuclear Steam Generator / Material / dx.doi.org/10.13182/NT81-A32832

Materials Requirements for Pressurized Water Reactor Steam Generator Tubing

Ph. Berge, J. R. Donati

Nuclear Technology / Volume 55 / Number 1 / October 1981 / Pages 88-104

Technical Paper / Materials Performance in Nuclear Steam Generator / Material / dx.doi.org/10.13182/NT81-A32833

Chemical Thermohydraulics of Steam Generating Systems

Paul Cohen

Nuclear Technology / Volume 55 / Number 1 / October 1981 / Pages 105-116

Technical Paper / Materials Performance in Nuclear Steam Generator / Material / dx.doi.org/10.13182/NT81-A32834

System Chemistry Considerations for Nuclear Steam Generators

Frederick, J. Pocock

Nuclear Technology / Volume 55 / Number 1 / October 1981 / Pages 117-123

Technical Paper / Materials Performance in Nuclear Steam Generator / Material / dx.doi.org/10.13182/NT81-A32835

The Implications for Condensate Purification of Operation at pH 9.6

R. Garnsey, D. J. Parry

Nuclear Technology / Volume 55 / Number 1 / October 1981 / Pages 124-134

Technical Paper / Materials Performance in Nuclear Steam Generator / Material / dx.doi.org/10.13182/NT81-A32836

Effects of Copper and Nickel Compounds on the Corrosion of Pressurized Water Reactor Steam Generator Materials

Earl L. White, Warren E. Berry

Nuclear Technology / Volume 55 / Number 1 / October 1981 / Pages 135-150

Technical Paper / Materials Performance in Nuclear Steam Generator / Material / dx.doi.org/10.13182/NT81-A32837

The Design and Construction of Boilers for Advanced Gas-Cooled Reactors in the United Kingdom

P. J. Cameron, J. Walters

Nuclear Technology / Volume 55 / Number 1 / October 1981 / Pages 151-162

Technical Paper / Materials Performance in Nuclear Steam Generator / Material / dx.doi.org/10.13182/NT81-A32838

Study on Hydrogen-Induced Cracking in the Heat-Affected Zone of Heavy Forgings Overlaid by Stainless Steel

K. Ohnishi, H. Tsukada, M. Kusuhashi, Y. Tanaka

Nuclear Technology / Volume 55 / Number 1 / October 1981 / Pages 163-177

Technical Paper / Materials Performance in Nuclear Steam Generator / Material / dx.doi.org/10.13182/NT81-A32839

Evaluation of Sodium Phosphate as A Denting Inhibitor

R. S. Pathania, E. G. McVey

Nuclear Technology / Volume 55 / Number 1 / October 1981 / Pages 178-190

Technical Paper / Materials Performance in Nuclear Steam Generator / Material / dx.doi.org/10.13182/NT81-A32840

Corrosion of Alloy 600 by Cationic Resin Beads

Martin W. Kendig, Hugh S. Isaacs

Nuclear Technology / Volume 55 / Number 1 / October 1981 / Pages 191-195

Technical Paper / Materials Performance in Nuclear Steam Generator / Material / dx.doi.org/10.13182/NT81-A32841

Pitting Corrosion of Nuclear Steam Generator Materials

P. J. King, D. P. Dautovich

Nuclear Technology / Volume 55 / Number 1 / October 1981 / Pages 196-206

Technical Paper / Materials Performance in Nuclear Steam Generator / Material / dx.doi.org/10.13182/NT81-A32842

Chemical Cleaning of the Nuclear Power Demonstration Unit Boiler

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

Nuclear Technology / Volume 55 / Number 1 / October 1981 / Pages 207-217

Technical Paper / Materials Performance in Nuclear Steam Generator / Material / dx.doi.org/10.13182/NT81-A32843

SNR 300 Experience in Steam Generator Materials

M. H. Knaap, H. C. D. Nieuwland, J. Vrijen, J. K. Van Westenbrugge, W. Husslage, C. P. Scheepens, J. W. Schinkel

Nuclear Technology / Volume 55 / Number 1 / October 1981 / Pages 218-227

Technical Paper / Materials Performance in Nuclear Steam Generator / Material / dx.doi.org/10.13182/NT81-A32844

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

Number 3

Table of Contents
Authors(Volker Drüke, Detlef Filges, Rahim Nabbi, Ralf D. Neef, Norbert Paul, Hartwig Schaal, J. F. Carew, D. K. Min, A. L. Aronson, Miroslav Havránek, Jochen Elzmann, Farid Bamdad, T. N. Ake, R. G. McAndrew, D. D. Whitney, H. Carlsen, D. N. Sah, Richard Simms, George S. Stanford, Charles L. Fink, James P. Regis, G. G. Wicks, David G. Franklin, B. A. Loomis, H. R. Thresh, G. L. Fogle, S. B. Gerber, B. C. Syrett, D. Cubicciotti, R. L. Jones, Yoshiaki Oka, Ichiroh Yanagisawa, Shigehiro An, A. M. Poindexter, Constantine P. Tzanos, T. K. Li, J. P. Ruiter, William R. Corcoran, Nancy J. Porter, James F. Church, Michael T. Cross, Walter M. Guinn, Katsuyuki Kawashima, Kotaro Inoue, Setsuo Kobayashi, Daniel Cubicciotti, B. C. Syrett, R. L. Jones, R. G. Johnson, J. W. Behrens, C. D. Bowman)
Comments on“Wash-1400: A Comparison of Experience and Prediction”(Gareth W. Parry)
Reply to “Comments on ‘Wash-1400: A Comparison of Experience and Prediction’ ”(G. S. Lellouche)
Further Information on“Wash-1400: A Comparison of Experience and Prediction”(Gerald S. Lellouche)
Theory of Magnetically Confined Plasmas(N. V. V. J. Swamy)
Fundamentals of Pipe Flow(K. Almenas)
Modern Physics(J. N. Anno)
Thermal Properties of Foods and Agricultural Materials(Clifford J. Cremers)
A User's Guide to Vacuum Technology(Clifford J. Cremers)

Heterogeneous Poisoning of the Critical HTGR Test Facility Kahter: A Study for the Initial Loading of Pebble Bed Power Reactors

Volker Drüke, Detlef Filges, Rahim Nabbi, Ralf D. Neef, Norbert Paul, Hartwig Schaal

Nuclear Technology / Volume 55 / Number 3 / December 1981 / Pages 549-564

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT81-A32798

Spectral Effects in the Extrapolation of Pressure Vessel Surveillance Capsule Measurements

J. F. Carew, D. K. Min, A. L. Aronson

Nuclear Technology / Volume 55 / Number 3 / December 1981 / Pages 565-567

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT81-A32799

A Posteriori Evaluation of the Coarse-Mesh Calculation Results in Boiling Water Reactor Dynamics

Miroslav Havránek, Jochen Elzmann

Nuclear Technology / Volume 55 / Number 3 / December 1981 / Pages 568-577

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT81-A32800

Analysis of Manual Depressurization of a Boiling Water Reactor Under Transient Condition

Farid Bamdad

Nuclear Technology / Volume 55 / Number 3 / December 1981 / Pages 578-582

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT81-A32801

Fuel Cycle Extension by Part-Length Control Rod Removal at Rancho Seco

T. N. Ake, R. G. McAndrew, D. D. Whitney

Nuclear Technology / Volume 55 / Number 3 / December 1981 / Pages 583-586

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT81-A32802

Radial Concentration and Effect on Temperature of Plutonium Formed in UO₂ During Irradiation

H. Carlsen, D. N. Sah

Nuclear Technology / Volume 55 / Number 3 / December 1981 / Pages 587-593

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT81-A32803

Fuel Motion in Experiments Simulating Liquid-Metal Fast Breeder Reactor Loss-of-Flow Accidents

Richard Simms, George S. Stanford, Charles L. Fink, James P. Regis

Nuclear Technology / Volume 55 / Number 3 / December 1981 / Pages 594-600

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT81-A32804

Vitrification of Simulated High-Level Radioactive Waste by a Slurry-Fed Ceramic Melter

G. G. Wicks

Nuclear Technology / Volume 55 / Number 3 / December 1981 / Pages 601-606

Technical Paper / Redioactive Waste Managment / dx.doi.org/10.13182/NT81-A32805

Economic Impact of Nuclear Core Materials Limitations

David G. Franklin

Nuclear Technology / Volume 55 / Number 3 / December 1981 / Pages 607-616

Technical Paper / Economic / dx.doi.org/10.13182/NT81-A32806

Design, Production, and Evaluation of a Zircaloy-Clad Uranium Target for an Intense Pulsed Neutron Source Application

B. A. Loomis, H. R. Thresh, G. L. Fogle, S. B. Gerber

Nuclear Technology / Volume 55 / Number 3 / December 1981 / Pages 617-627

Technical Paper / Material / dx.doi.org/10.13182/NT81-A32807

The Effects of Texture and Surface Condition on the Iodine Stress Corrosion Cracking Susceptibility of Unirradiated Zircaloy-2

B. C. Syrett, D. Cubicciotti, R. L. Jones

Nuclear Technology / Volume 55 / Number 3 / December 1981 / Pages 628-641

Technical Paper / Material / dx.doi.org/10.13182/NT81-A32808

A Design Study of the Neutron Irradiation Facility for Boron Neutron Capture Therapy

Yoshiaki Oka, Ichiroh Yanagisawa, Shigehiro

Nuclear Technology / Volume 55 / Number 3 / December 1981 / Pages 642-655

Technical Paper / Radioisotopes and Isotope / dx.doi.org/10.13182/NT81-A32809

Thermal Response of a Flat Plate of Finite Thickness Immersed in a Fluid with Oscillating Temperature

A. M. Poindexter

Nuclear Technology / Volume 55 / Number 3 / December 1981 / Pages 656-661

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT81-A32810

Optimization of a Variable Flow Allocation Scheme in Heterogeneous Liquid-Metal Fast Breeder Reactors

Constantine P. Tzanos

Nuclear Technology / Volume 55 / Number 3 / December 1981 / Pages 662-673

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT81-A32811

Automated In-Line Measurement of Plutonium Solutions in a Plutonium Purification Process

T. K. Li

Nuclear Technology / Volume 55 / Number 3 / December 1981 / Pages 674-682

Technical Paper / Analyse / dx.doi.org/10.13182/NT81-A32812

Weighing of Heavy Vessels Using Strain Gauges

J. P. Ruiter

Nuclear Technology / Volume 55 / Number 3 / December 1981 / Pages 683-689

Technical Paper / Technique / dx.doi.org/10.13182/NT81-A32813

The Critical Safety Functions and Plant Operation

William R. Corcoran, Nancy J. Porter, James F. Church, Michael T. Cross, Walter M. Guinn

Nuclear Technology / Volume 55 / Number 3 / December 1981 / Pages 690-712

Technical Paper / Education / dx.doi.org/10.13182/NT81-A32814

A Fast Reactor Core Concept Using an Internal Blanket

Katsuyuki Kawashima, Kotaro Inoue, Setsuo Kobayashi

Nuclear Technology / Volume 55 / Number 3 / December 1981 / Pages 713-719

Technical Note / Fission Reactor / dx.doi.org/10.13182/NT81-A32815

Influence of Surface Condition on Crack Initiation in Iodine-Induced Stress Corrosion Cracking of Zircaloys

Daniel Cubicciotti, B. C. Syrett, R. L. Jones

Nuclear Technology / Volume 55 / Number 3 / December 1981 / Pages 720-723

Technical Note / Material / dx.doi.org/10.13182/NT81-A32816

Source Imaging Using Neutron Pinhole Cameras Based on Position-Sensitive Proportional Counters

Nuclear Technology / Volume 55 / Number 3 / December 1981 / Pages 724-727

Technical Note / Technique / dx.doi.org/10.13182/NT81-A32817