American Nuclear Society
Join ANS|Member Center|ANS Store|Contact Us
Home

Home / Publications / Journals / Nuclear Technology / Volume 28

Volume 28

Number 1 | Number 2 | Number 3

Number 1

Power Burst Facility Fuel Studies

J. T. Cole, R. E. Wood

Nuclear Technology / Volume 28 / Number 1 / January 1976 / Pages 9-22

Technical Paper / Fuels for Pulsed Reactor / Fuel / dx.doi.org/10.13182/NT76-A31535

(U,Zr)C-Graphite Fuel for TREAT Converter Studies

Keith V. Davidson

Nuclear Technology / Volume 28 / Number 1 / January 1976 / Pages 23-30

Technical Paper / Fuels for Pulsed Reactor / Fuel / dx.doi.org/10.13182/NT76-A31536

Fuel Elements for Pulsed TRIGA® Research Reactors

Massoud T. Simnad, Fabian C. Foushee, Gordon B. West

Nuclear Technology / Volume 28 / Number 1 / January 1976 / Pages 31-56

Technical Paper / Fuels for Pulsed Reactor / Fuel / dx.doi.org/10.13182/NT76-A31537

Material Property Determination for Fast Pulsed Reactor Fuels by Rapid Fission Heating

J. A. Reuscher, T. R. Schmidt

Nuclear Technology / Volume 28 / Number 1 / January 1976 / Pages 57-67

Technical Paper / Fuels for Pulsed Reactor / Fuel / dx.doi.org/10.13182/NT76-A31538

A Measurement of Temperature-Dependent Internal Friction for Uranium, U—0.78 wt% Ti, U—6 wt% Mo, and U—10 wt% Mo

E. T. Laats, T. R. Schmidt, J. A. Reuscher

Nuclear Technology / Volume 28 / Number 1 / January 1976 / Pages 68-76

Technical Paper / Fuels for Pulsed Reactor / Fuel / dx.doi.org/10.13182/NT76-A31539

Fabrication of Uranium-Molybdenum Alloy Fuels for Pulsed Reactors

James M. Taub

Nuclear Technology / Volume 28 / Number 1 / January 1976 / Pages 77-86

Technical Paper / Fuels for Pulsed Reactor / Fuel / dx.doi.org/10.13182/NT76-A31540

Summary of Unpublished Presentations for Fuels for Pulsed Reactors

James A. Horak

Nuclear Technology / Volume 28 / Number 1 / January 1976 / Pages 87-91

Technical Paper / Fuels for Pulsed Reactor / Fuel / dx.doi.org/10.13182/NT76-A31541

Clinch River Breeder Reactor Breeding Characteristics

G. C. Tillett, Jr., A. R. Buhl

Nuclear Technology / Volume 28 / Number 1 / January 1976 / Pages 92-97

Technical Paper / Fuels for Pulsed Reactor / Reactor / dx.doi.org/10.13182/NT76-A31542

Fusion-Fission Hybrid Concepts for Laser-Induced Fusion

James Maniscalco

Nuclear Technology / Volume 28 / Number 1 / January 1976 / Pages 98-107

Technical Paper / Fuels for Pulsed Reactor / Reactor / dx.doi.org/10.13182/NT76-A31543

A Method for Generating a Control Rod Program for Boiling Water Reactors

Toshio Kawai, Hiroshi Motoda, Takashi Kiguchi, Michihiro Ozawa

Nuclear Technology / Volume 28 / Number 1 / January 1976 / Pages 108-118

Technical Paper / Fuels for Pulsed Reactor / Reactor / dx.doi.org/10.13182/NT76-A31544

Hydrodynamic Containment for Underground Nuclear Power Plants

J. M. Cardito, E. V. Somers, J. H. McWhirter

Nuclear Technology / Volume 28 / Number 1 / January 1976 / Pages 119-126

Technical Paper / Fuels for Pulsed Reactor / Reactor Siting / dx.doi.org/10.13182/NT76-A31545

Fission Gas Behavior in Oxide Fuel Elements of Fast Breeder Reactors

H. Zimmermann

Nuclear Technology / Volume 28 / Number 1 / January 1976 / Pages 127-133

Technical Paper / Fuels for Pulsed Reactor / Fuel / dx.doi.org/10.13182/NT76-A31546

Statistical and Metallurgical Analyses of Experimental Mark-IA Driver Fuel Element Cladding Failures in the Experimental Breeder Reactor II

N. J. Olson, C. M. Walter, W. N. Beck

Nuclear Technology / Volume 28 / Number 1 / January 1976 / Pages 134-151

Technical Paper / Fuels for Pulsed Reactor / Fule / dx.doi.org/10.13182/NT76-A31547

Computational Experiments with a Californium-252 Source for Possible Use in Neutron Radiography

D. Kedem, M. Lemanska

Nuclear Technology / Volume 28 / Number 1 / January 1976 / Pages 152-158

Technical Paper / Fuels for Pulsed Reactor / Radioisotope / dx.doi.org/10.13182/NT76-A31548

Some Studies of Reflector Construction and Electronics Configurations for Optimizing Pulse-Height and Pulse-Shape Resolution in Alpha Liquid-Scintillation Spectrometry

John W. McKlveen, W. J. McDowell

Nuclear Technology / Volume 28 / Number 1 / January 1976 / Pages 159-164

Technical Paper / Fuels for Pulsed Reactor / Instrument / dx.doi.org/10.13182/NT76-A31549

An In-Line Station for Volume Calibration of Raschig-Ring-Filled Storage Tanks for Fissile Solution

Robert E. Rothe, Louis W. Doher, A. L. Johnston

Nuclear Technology / Volume 28 / Number 1 / January 1976 / Pages 165-171

Technical Note / Fuels for Pulsed Reactor / Chemical Processing / dx.doi.org/10.13182/NT76-A31550

Laboratory Experiments to Check Cooling Tower Computer Models

Heinrich Werle

Nuclear Technology / Volume 28 / Number 1 / January 1976 / Page 172

Technical Note / Fuels for Pulsed Reactor / Technique / dx.doi.org/10.13182/NT76-A31551

Number 2

  • Table of Contents
  • Authors(W. F. Oberbeck, Jr., K. G. Mayhan, D. R. Edwards, J. R. Lopata, J. F. Montle, D. R. Leritz, A. K. Bhattacharyya, S.K. Chaudhuri, Karl Hornyik, G. Karsten, G.Mühling, H.Plitz, G.Giacchetti, C. Sari, C. T. Walker, Hirotaka Furuya, Masumichi Koizumi, William Primak, T. T. Anderson, J. W. Dini, H.R. Johnson, C. W. Schoenfelder, C. Sari, G. Schumacher, E.Elias, Y. Segal, A. Notea, P. K. Sarkar, K. N. Kirthi, A. K. Ganguly, John R. Phillips)
  • Corrigendum

Simulated and Simultaneous Loss-of-Coolant Accident Testing of Protective Coatings for the Nuclear Industry

W. F. Oberbeck, Jr., K. G. Mayhan, D. R. Edwards, J. R. Lopata, J. F. Montle, D. R. Leritz

Nuclear Technology / Volume 28 / Number 2 / February 1976 / Pages 183-193

Technical Paper / Reactor / dx.doi.org/10.13182/NT76-A31558

The Probability of a Turbine Missile Hitting a Particular Region of a Nuclear Power Plant

A. K. Bhattacharyya, S. K. Chaudhuri

Nuclear Technology / Volume 28 / Number 2 / February 1976 / Pages 194-198

Technical Paper / Reactor / dx.doi.org/10.13182/NT76-A31559

Hazards to Nuclear Plants from Off-Site Release of Toxic Vapors

Karl Hornyik

Nuclear Technology / Volume 28 / Number 2 / February 1976 / Pages 199-207

Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT76-A31560

Strategy, Design Basis, and Results of the Carbide Program for SNR

G. Karsten, G. Mühling, H. Plitz

Nuclear Technology / Volume 28 / Number 2 / February 1976 / Pages 208-215

Technical Paper / Fuel / dx.doi.org/10.13182/NT76-A31561

Actinides and Fission Products Distribution in Fast Breeder Nitride Fuel

G. Giacchetti, C. Sari, C. T. Walker

Nuclear Technology / Volume 28 / Number 2 / February 1976 / Pages 216-225

Technical Paper / Fuel / dx.doi.org/10.13182/NT76-A31562

Surface Diffusion of Plutonium on Uranium Dioxide

Hirotaka Furuya, Masumichi Koizumi

Nuclear Technology / Volume 28 / Number 2 / February 1976 / Pages 226-234

Technical Paper / Material / dx.doi.org/10.13182/NT76-A31563

Metamictization of Lithium Niobate by Thermal Neutrons

William Primak, T. T. Anderson

Nuclear Technology / Volume 28 / Number 2 / February 1976 / Pages 235-248

Technical Paper / Material / dx.doi.org/10.13182/NT76-A31564

Corrosion Behavior, Mechanical Properties, and Long-Term Aging of Nickel-Plated Uranium

J. W. Dini, H. R. Johnson, C. W. Schoenfelder

Nuclear Technology / Volume 28 / Number 2 / February 1976 / Pages 249-255

Technical Paper / Material / dx.doi.org/10.13182/NT76-A31565

Thermal Diffusion of Oxygen in PuO2-y

C.Sari, G.Schumacher

Nuclear Technology / Volume 28 / Number 2 / February 1976 / Pages 256-260

Technical Paper / Material / dx.doi.org/10.13182/NT76-A31566

Transmission of Gamma Radiation Through Finite Cylindrical Barriers

E. Elias, Y. Segal, A. Notea

Nuclear Technology / Volume 28 / Number 2 / February 1976 / Pages 261-269

Technical Paper / Radiation / dx.doi.org/10.13182/NT76-A31567

A Proton Recoil Scintillation Technique for Estimating Neutron Energy Spectra

P. K. Sarkar, K. N. Kirthi, A. K. Ganguly

Nuclear Technology / Volume 28 / Number 2 / February 1976 / Pages 270-281

Technical Paper / Technique / dx.doi.org/10.13182/NT76-A31568

Improved Nondestructive Determination of Two-Dimensional Radial Isotopic Distributions in Irradiated Fuel Pins

John R. Phillips

Nuclear Technology / Volume 28 / Number 2 / February 1976 / Pages 282-290

Technical Paper / Technique / dx.doi.org/10.13182/NT76-A31569

Number 3

  • Table of Contents
  • Authors(P. Patriarca, W. R. Martin, G. W. Cunningham, J. C. Whipple, C. N. Spalaris, W. G. Schuetzenduebel, S. Vandeth, R. L. Hemmings, Hans W. Fricker, John R. Weeks, W. D. Fletcher, D. D. Malinowski, R. W. McClung, G.M. Slaughter, C. N. Spalaris, A. F. Lillie, P. A. Carlson, W. K. Kratzer, G. J. Theus, J. H. DeVan, J. C. Griess, F. N. Mazandarany, P. L. Rittenhouse, H. G. A. Bates, W. Betteridge, R. H. Cook, L. W. Graham, D. F. Lupton, K. Natesan, O. K. Chopra, T. F. Kassner, Keishi Matsumoto, Yoshio Ohta, Tadayuki Kataoka, Shigeji Yagi, Katsumi Suzuki, Teruo Yukitoshi, Taishi Moroishi, Kunihiko Yoshikawa, Yoshiaki Shida, J. A. Shields, Jr., K. J. Longua, M. G. Robin, C. R. Brinkman, R. K.Williams, R. L. Klueh, T. L. Hebble, Teruo Yukitoshi, Taishi Moroishi, Isamu Koizumi, Takashi Abe, Kunihiko Yoshikawa, Yoshiaki Shida, P.Patriarca, S. D. Harkness, J. M. Duke, L. R. Cooper)
  • Preface: Nuclear Steam Generators(P. Patriarca, W. R. Martin)

Materials Development for Advanced Reactors

G. W. Cunningham

Nuclear Technology / Volume 28 / Number 3 / March 1976 / Pages 301-304

Technical Paper / Reactor / dx.doi.org/10.13182/NT76-A31512

Design of the Clinch River Breeder Reactor Plant Steam Generators

J. C. Whipple, C. N. Spalaris

Nuclear Technology / Volume 28 / Number 3 / March 1976 / Pages 305-314

Technical Paper / Reactor / dx.doi.org/10.13182/NT76-A31513

High-Temperature Gas-Cooled Reactor Steam Generator Design

W. G. Schuetzenduebel

Nuclear Technology / Volume 28 / Number 3 / March 1976 / Pages 315-327

Technical Paper / Reactor / dx.doi.org/10.13182/NT76-A31514

Materials in Candu Steam Generators from the Designer's Point of View

S. Vandeth, R. L. Hemmings

Nuclear Technology / Volume 28 / Number 3 / March 1976 / Pages 328-338

Technical Paper / Reactor / dx.doi.org/10.13182/NT76-A31515

Design and Manufacturing Experience for the German Thorium High-Temperature Reactor 300-MW(e) Steam Generator

Hans W. Fricker

Nuclear Technology / Volume 28 / Number 3 / March 1976 / Pages 339-347

Technical Paper / Reactor / dx.doi.org/10.13182/NT76-A31516

Materials Performance in Operating Pressurized Water Reactor Steam Generators

John R. Weeks

Nuclear Technology / Volume 28 / Number 3 / March 1976 / Pages 348-355

Technical Paper / Reactor / dx.doi.org/10.13182/NT76-A31517

Operating Experience with Westinghouse Steam Generators

W. D. Fletcher, D. D. Malinowski

Nuclear Technology / Volume 28 / Number 3 / March 1976 / Pages 356-373

Technical Paper / Reactor / dx.doi.org/10.13182/NT76-A31518

Fabrication and Inspection Development for Clinch River Breeder Reactor Plant Steam Generators

R. W. McClung, G. M. Slaughter, C. N. Spalaris, A. F. Lillie

Nuclear Technology / Volume 28 / Number 3 / March 1976 / Pages 374-382

Technical Paper / Reactor / dx.doi.org/10.13182/NT76-A31519

N Reactor Steam Generator Performance

P. A. Carlson, W. K. Kratzer

Nuclear Technology / Volume 28 / Number 3 / March 1976 / Pages 383-387

Technical Paper / Reactor / dx.doi.org/10.13182/NT76-A31520

Caustic Stress Corrosion Cracking of Inconel-600, Incoloy-800, and Type 304 Stainless Steel

G. J. Theus

Nuclear Technology / Volume 28 / Number 3 / March 1976 / Pages 388-397

Technical Paper / Reactor / dx.doi.org/10.13182/NT76-A31521

Clinch River Breeder Reactor Environmental Effects-General Water-Side Corrosion

J. H. DeVan, J. C. Griess

Nuclear Technology / Volume 28 / Number 3 / March 1976 / Pages 398-405

Technical Paper / Reactor / dx.doi.org/10.13182/NT76-A31522

Effects of Service Environments on the Behavior of High-Temperature Gas-Cooled Reactor Steam Generator Structural Materials

F. N. Mazandarany, P. L. Rittenhouse

Nuclear Technology / Volume 28 / Number 3 / March 1976 / Pages 406-423

Technical Paper / Reactor / dx.doi.org/10.13182/NT76-A31523

The Behavior of Metals in High-Temperature Reactor Helium for Steam Generators

H. G. A. Bates, W. Betteridge, R. H. Cook, L. W. Graham, D. F. Lupton

Nuclear Technology / Volume 28 / Number 3 / March 1976 / Pages 424-440

Technical Paper / Reactor / dx.doi.org/10.13182/NT76-A31524

Compatibility of Fe-2¼ wt% Cr-1 wt% Mo Steel in a Sodium Environment

K. Natesan, O. K. Chopra, T. F. Kassner

Nuclear Technology / Volume 28 / Number 3 / March 1976 / Pages 441-451

Technical Paper / Reactor / dx.doi.org/10.13182/NT76-A31525

Carbon Transfer Behavior of Materials for Liquid-Metal Fast Breeder Reactor Steam Generators

Keishi Matsumoto, Yoshio Ohta, Tadayuki Kataoka, Shigeji Yagi, Katsumi Suzuki, Teruo Yukitoshi, Taishi Moroishi, Kunihiko Yoshikawa, Yoshiaki Shida

Nuclear Technology / Volume 28 / Number 3 / March 1976 / Pages 452-470

Technical Paper / Reactor / dx.doi.org/10.13182/NT76-A31526

The Effects of Ten Years Experimental Breeder Reactor II Service on 2¼ Cr-1 Mo Steel

J. A. Shields, Jr., K. J. Longua

Nuclear Technology / Volume 28 / Number 3 / March 1976 / Pages 471-481

Technical Paper / Reactor / dx.doi.org/10.13182/NT76-A31527

French Steam Generator Experience-Phenix and Beyond

M. G. Robin

Nuclear Technology / Volume 28 / Number 3 / March 1976 / Pages 482-489

Technical Paper / Reactor / dx.doi.org/10.13182/NT76-A31528

Mechanical and Physical Properties of 2¼ Cr-1 Mo Steel in Support of Clinch River Breeder Reactor Plant Steam Generator Design

C. R. Brinkman, R. K. Williams, R. L. Klueh, T. L. Hebble

Nuclear Technology / Volume 28 / Number 3 / March 1976 / Pages 490-505

Technical Paper / Reactor / dx.doi.org/10.13182/NT76-A31529

Comparison of Various Chromium-Molybdenum Low-Alloy Steels for Liquid-Metal Fast Breeder Reactor Steam Generators

Teruo Yukitoshi, Taishi Moroishi, Isamu Koizumi, Takashi Abe, Kunihiko Yoshikawa, Yoshiaki Shida

Nuclear Technology / Volume 28 / Number 3 / March 1976 / Pages 506-515

Technical Paper / Reactor / dx.doi.org/10.13182/NT76-A31530

U.S. Advanced Materials Development Program for Steam Generators

P. Patriarca, S. D. Harkness, J. M. Duke, L. R. Cooper

Nuclear Technology / Volume 28 / Number 3 / March 1976 / Pages 516-536

Technical Paper / Reactor / dx.doi.org/10.13182/NT76-A31531

 

Home|Contact Us|Invoice Payment|Nuclear Links

Privacy Policy|Terms of Use