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Volume 35

Number 1 | Number 2 | Number 3

Number 1

  • Table of Contents
  • Authors(D. C. Arwood, T. W. Kerlin, G. P. Mulholland, T. F. Luera, A. De La Paz, Balabhadra Misra, Victor A. Maroni, Mohamed A. Abdou, Jungchung Jung, F. D’Annucci, C. Sari, G. Schumacher, Paul B. Abramson, E. D. Clayton, H. K. Clark, D. W. Magnuson, J. H. Chalmers, Gordon Walker, N. Ketzlach, Ryohei Kiyose, C. L. Brown, D. R. Smith, R. Artigas, C. Devillers, P. Blum, T. Shimooke, K. Matsumoto, J. T. A. Roberts, E. Smith, N. Fuhrman, D. Cubicciotti, C. Sari, U. Benedict, G. Giacchetti, Hj. Matzke, K. Richter, C. Sari, H. E. Schmidt, Mark B. Triplett, E. C. Beahm, C. A. Culpepper, John W. Wilson, Fred M. Denn, W. Van Witzenburg, L. G. J. Janssen, J. Prij)
  • Creep-Rupture Properties of 20% Cold-Worked Type 316 Stainless Steel After High Fluence Neutron Irradiation(R. L. Fish)
  • Corrigendum

A Mathematical Model for an Integral Economizer U-Tube Steam Generator

D. C. Arwood, T. W. Kerlin

Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 12-32

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31847

Thermal Shock Effects in Fast Burst Reactors

G. P. Mulholland, T. F. Luera, A. De La Paz

Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 33-39

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31848

Isotopic Enrichment of Plasma Exhausts from Controlled Thermonuclear Reactors by Cryogenic Distillation

Balabhadra Misra, Victor A. Maroni

Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 40-50

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31849

Nuclear Analysis of a Tokamak Experimental Power Reactor Conceptual Design

Mohamed A. Abdou, Jungchung Jung

Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 51-79

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31850

Migration of Metallic Fission Products in Reactor Oxide Fuels

F. D’Annucci, C. Sari, G. Schumacher

Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 80-86

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31851

The Importance of Heat Transfer in Hypothetical Core Disruptive Accident Analysis

Paul B. Abramson

Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 87-96

Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT77-A31852

Basis for Subcritical Limits in Proposed Criticality Safety Standard for Mixed Oxides

E. D. Clayton, H. K. Clark, D. W. Magnuson,+ J. H. Chalmers,† Gordon Walker,‡ N. Ketzlach, Ryohei Kiyose,++ C. L. Brown, D. R. Smith,††, R. Artigas ‡‡

Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 97-111

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT77-A31853

Neutron Multiplication and Shielding Problems in Pressurized Water Reactor Spent Fuel Shipping Casks

C. Devillers, P. Blum

Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 112-118

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT77-A31854

Probability Distributions of Peak-Clad Temperature and Cladding Oxidation Thickness in Loss-of-Coolant Accidents for a Typical Boiling Water Reactor

T. Shimooke, K. Matsumoto

Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 119-130

Technical Paper / Fuel / dx.doi.org/10.13182/NT77-A31855

On the Pellet-Cladding Interaction Phenomenon

J. T. A. Roberts, E. Smith, N. Fuhrman, D. Cubicciotti

Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 131-144

Technical Paper / Fuel / dx.doi.org/10.13182/NT77-A31856

Simulation Study of the Restructuring of Advanced Fuel Heated in a Radial Temperature Gradient

C. Sari

Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 145-153

Technical Paper / Fuel / dx.doi.org/10.13182/NT77-A31857

Study of Uranium-Plutonium Carbide-Based Fuel Simulating High Burnup

U. Benedict, G. Giacchetti, Hj. Matzke, K. Richter, C. Sari, H. E. Schmidt

Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 154-161

Technical Paper / Fuel / dx.doi.org/10.13182/NT77-A31858

Simulation of the Nuclear Power Economy

Mark B. Triplett

Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 162-172

Technical Paper / Economic / dx.doi.org/10.13182/NT77-A31859

Basic Compatibility Studies of Advanced Fuels with 3d Transition Metals

E. C. Beahm, C. A. Culpepper

Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 173-177

Technical Paper / Material / dx.doi.org/10.13182/NT77-A31860

Methods of Shield Analysis for Protection Against Electrons in Space

John W. Wilson, Fred M. Denn

Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 178-183

Technical Paper / Shielding / dx.doi.org/10.13182/NT77-A31861

On the Effective Temperature of an Expanding Tube with a Radial Temperature Gradient over the Wall

W. Van Witzenburg, L. G. J. Janssen, J. Prij

Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 184-187

Technical Note / Reactor / dx.doi.org/10.13182/NT77-A31862

Number 2

  • Table of Contents
  • Authors(T. D. Gulden, H. Nickel, G. W. Weber, R. L. Beatty, V. J. Tennery, W. J. Lackey, D. P. Stinton, J. D. Sease, H. Huschka, P. Vygen, P. L. Allen, L. H. Ford, J. V. Shennan, J. Linke, K. Koizlik, H. Nickel, R. L. R. Lefevre, M. S. T. Price, K. Wallisch, P. Koss, W. Delle, K. Koizlik, M. S. T. Price, E. Wallura, E. A. Wolfrum, H. Nickel, E. Pollmann, J. Pelissier, C. S. Yust, J. L. Kaae, P. Krautwasser, H. Nickel, R. J. Price, C. S. Morgan, G. L. Powell, D. P. Harmon, C. B. Scott, R. A. Bradley, B. A. Thiele, J. L. Kaae, J. L. Kaae, R. E. Bullock, C. B. Scott, D. P. Harmon, Karl Bongartz, A. Strigl, E. Proksch, M. Wagner-Löffler, C. L. Smith, H. Grübmeier, A. Naoumidis, B. A. Thiele, F. J. Homan, T. B. Lindemer, E. L. Long, Jr., T. N. Tiegs, R. L. Beatty, C. B. Scott, D. P. Harmon, M. T. Morgan, A. P. Malinauskas, D. Stöver, R. Hecker, P. D. Smith, R. G. Steinke, D. D. Jensen T. Hama, H. Nabielek, P. E. Brown, P. Offermann, Marie-Louise Pointud, Pierre Chenebault, B. F. Myers, N. L. Baldwin, W. E. Bell, E. Groos, G. Mielken, R. Duwe, A. Müller, M. Will, K. Röllig, C. M. Hollabaugh, L. A. Wahman, R. D. Reiswig, R. W. White, P. Wagner, J. L. Kaae, S. A. Sterling, L. Yang, R. Förthmann, H. Grübmeier, D. Stöver, Werner Katscher, H. Nickel, T. D. Gulden)
  • Foreword: Coated Particle Fuels
  • Preface: Coated Particle Fuels(T. D. Gulden, H. Nickel)
  • Concluding Remarks: Coated Particle Fuels(H. Nickel, T. D. Gulden)

Processing and Composition Control of Weak-Acid-Resin-Derived Fuel Microspheres

G. W. Weber, R. L. Beatty, V. J. Tennery

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 217-226

Fabrication / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31881

Improved Gas Distributor for Coating High-Temperature Gas-Cooled Reactor Fuel Particles

W. J. Lackey, D. P. Stinton, J. D. Sease

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 227-237

Fabrication / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31882

Coated Fuel Particles: Requirements and Status of Fabrication Technology

H. Huschka, P. Vygen

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 238-245

Fabrication / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31883

Nuclear Fuel Coated Particle Development in the Reactor Fuel Element Laboratories of the U.K. Atomic Energy Authority

P. L. Allen, L. H. Ford, J. V. Shennan

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 246-253

Fabrication / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31884

Fundamentals on the Agglomerate Model and Its Relation to the Physical Properties of Pyrocarbon

J. Linke, K. Koizlik, H. Nickel

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 257-262

Pyrocarbon / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31885

Coated Nuclear Fuel Particles: The Coating Process and Its Model

R. L. R. Lefevre, M. S. T. Price

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 263-278

Pyrocarbon / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31886

Automatic Size Analysis of Coated Fuel Particles

K. Wallisch, P. Koss

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 279-283

Pyrocarbon / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31887

Quality Control Techniques for Pyrocarbon

W. Delle, K. Koizlik, M. S. T. Price U.K., E. Wallura

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 284-292

Pyrocarbon / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31888

A Quantitative Chemical Method for the Determination of the Disordered Carbon Component in Pyrocarbon Coatings of Fuel Particles

E. A. Wolfrum, H. Nickel

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 293-300

Pyrocarbon / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31889

Transmission Electron Microscopy of Pyrocarbon Coatings

E. Pollmann, J. Pelissier, C. S. Yust, J. L. Kaae

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 301-309

Pyrocarbon / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31890

Influence of Porosity on the Irradiation Performance of Pyrocarbon Coatings

P. Krautwasser, H. Nickel

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 310-319

Pyrocarbon / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31891

Properties of Silicon Carbide for Nuclear Fuel Particle Coatings

R. J. Price

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 320-336

Pyrocarbon / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31892

Preliminary Examination of the Helium Permeability of Pyrocarbon Coatings

C. S. Morgan, G. L. Powell

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 337-339

Pyrocarbon / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31893

Properties Influencing High-Temperature Gas-Cooled Reactor Coated Fuel Particle Performance

D. P. Harmon, C. B. Scott

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 343-352

Performance and Performance Modeling / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31894

Neutron-Induced Permeability of Pyrocarbon-Coated High-Temperature Gas-Cooled Reactor Fuel Particles

R. A. Bradley, B. A. Thiele

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 353-358

Performance and Performance Modeling / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31895

The Mechanical Behavior of Biso-Coated Fuel Particles During Irradiation. Part I: Analysis of Stresses and Strains Generated in the Coating of a Biso Fuel Particle During Irradiation

J. L. Kaae

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 359-367

Performance and Performance Modeling / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31896

The Mechanical Behavior of Biso-Coated Fuel Particles During Irradiation. Part II: Prediction of Biso Particle Behavior During Irradiation with a Stress-Analysis Model

J. L. Kaae, R. E. Bullock, C. B. Scott, D. P. Harmon

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 368-378

Performance and Performance Modeling / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31897

Improvement of a Method for Predicting Failure Rates of Coated Particles During Irradiation

Karl Bongartz

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 379-385

Performance and Performance Modeling / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31898

Restoration of Carbon Monoxide Equilibrium in Porous Oxide High-Temperature Reactor Fuel Particles

A. Strigl, E. Proksch

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 386-391

Performance and Performance Modeling / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31899

Amoeba Behavior of UO2 Coated Particle Fuel

M. Wagner-Löffler

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 392-402

Performance and Performance Modeling / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31900

Migration of ThO2 Kernels Under the Influence of a Temperature Gradient

C. L. Smith

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 403-412

Performance and Performance Modeling / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31901

Silicon Carbide Corrosion in High-Temperature Gas-Cooled Reactor Fuel Particles

H. Grübmeier, A. Naoumidis, B. A. Thiele

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 413-427

Performance and Performance Modeling / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31902

Stoichiometric Effects on Performance of High-Temperature Gas-Cooled Reactor Fuels from the U-C-O System

F. J. Homan, T. B. Lindemer, E. L. Long, Jr., T. N. Tiegs, R. L. Beatty

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 428-441

Performance and Performance Modeling / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT35-428

Irradiation Performance of Fort St. Vrain High-Temperature Gas-Cooled Reactor Fuel in Capsule F-30

C. B. Scott, D. P. Harmon

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 442-454

Performance and Performance Modeling / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31904

Cesium Release and Transport in Biso-Coated Fuel Particles

M. T. Morgan, A. P. Malinauskas

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 457-464

Fission Product Release / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31905

Cesium Release Data for Biso-Coated Particles

D. Stöver, R. Hecker

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 465-474

Fission Product Release / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31906

Release of Metallic Fission Products from Multilayered Coated Particles

P. D. Smith, R. G. Steinke, D. D. Jensen, T. Hama

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 475-482

Fission Product Release / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31907

Silver Release from Coated Particle Fuel

H. Nabielek, P. E. Brown, P. Offermann

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 483-493

Fission Product Release / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT35-483

Emission of Fission Gases by Failed Coated Oxide Fuel Particles

Marie-Louise Pointud, Pierre Chenebault

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 494-500

Fission Product Release / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31909

Fission Gas Release from Fuel Particles and Fuel Rods

B. F. Myers, N. L. Baldwin, W. E. Bell

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 501-508

Fission Product Release / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31910

Fission Product Release from Coated Particles Embedded in Spherical Fuel Elements for High-Temperature Reactors

E. Groos, G. Mielken, R. Duwe, A. Müller, M. Will

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 509-515

Fission Product Release / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31911

Release of Rare Fission Gases from Spherical Elements with Coated Fuel Particles

K. Röllig

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 516-523

Fission Product Release / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31912

Chemical Vapor Deposition of ZrC Made by Reactions of ZrCl4 with CH4 and with C3H6

C. M. Hollabaugh, L. A. Wahman, R. D. Reiswig, R. W. White, P. Wagner

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 527-535

Advanced and Improved Fuel and Application / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31913

Improvements in the Performance of Nuclear Fuel Particles Offered by Silicon-Alloyed Carbon Coatings

J. L. Kaae, S. A. Sterling, L. Yang

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 536-547

Advanced and Improved Fuel and Application / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31914

Metallic Fission Product Retention of Coated Particles with Ceramic Kernel Additives

R. Förthmann, H. Grübmeier, D. Stöver

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 548-556

Advanced and Improved Fuel and Application / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31915

Coated Particle Fuel Element for Pressurized Water Reactors

Werner Katscher

Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 557-563

Advanced and Improved Fuel and Application / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31916

Number 3

  • Table of Contents
  • Authors(H. Jüntgen, K. H. van Heek, Charles Yung Fen Chang, John Skears, J. N. Chung, P. S. Ayyaswamy, J. J. Koelling, G. E. Hansen, C. C. Byers, E. E. Gruber, Bal Raj Sehgal, Joseph A. Naser, Ching-lu Lin, Walter B. Loewenstein, R. M. Alire, J. K. Fink, J. J. Heiberger, R. Kumar, R. A. Blomquist, G. Schulze, H. Würz, H. J. Petroski)
  • Progress on the Full-Scale Testing Program(Robert M. Jefferson)

A Technical Scale Gas Generator for Steam Gasification of Coal Using Nuclear Heat

H. Jüntgen, K. H. Van Heek

Nuclear Technology / Volume 35 / Number 3 / October 1977 / Pages 581-590

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31867

SOPHT—A Computer Model for CANDU-PHWR Heat Transport Networks and Their Control

Charles Yung Fen Chang, John Skears

Nuclear Technology / Volume 35 / Number 3 / October 1977 / Pages 591-602

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31868

The Effect of Internal Circulation on the Heat Transfer of a Nuclear Reactor Containment Spray Droplet

J. N. Chung, P. S. Ayyaswamy

Nuclear Technology / Volume 35 / Number 3 / October 1977 / Pages 603-610

Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31869

Fission and Explosive Energy Releases of PuO2, PuO2-UO2, UO2, and UO3 Assemblies

J. J. Koelling, G. E. Hansen, C. C. Byers

Nuclear Technology / Volume 35 / Number 3 / October 1977 / Pages 611-616

Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT77-A31870

A Generalized Parametric Model for Transient Gas Release and Swelling in Oxide Fuels

E. E. Gruber

Nuclear Technology / Volume 35 / Number 3 / October 1977 / Pages 617-634

Technical Paper / Fuel / dx.doi.org/10.13182/NT77-A31871

Thorium-Based Fuels in Fast Breeder Reactors

Bal Raj Sehgal, Joseph A. Naser, Ching-Lu Lin, Walter B. Loewenstein

Nuclear Technology / Volume 35 / Number 3 / October 1977 / Pages 635-650

Technical Paper / Fuel / dx.doi.org/10.13182/NT77-A31872

Transport of Deuterium in Nb—1 wt% Zr

R. M. Alire

Nuclear Technology / Volume 35 / Number 3 / October 1977 / Pages 651-655

Technical Paper / Material / dx.doi.org/10.13182/NT77-A31873

Interactions of Refractories and Reactor Materials with Sodium

J. K. Fink, J. J. Heiberger, R. Kumar, R. A. Blomquist

Nuclear Technology / Volume 35 / Number 3 / October 1977 / Pages 656-662

Technical Paper / Material / dx.doi.org/10.13182/NT77-A31874

In-Line Determination of Fissile Material in High-Activity Solutions

G. Schulze, H. Würz

Nuclear Technology / Volume 35 / Number 3 / October 1977 / Pages 663-670

Technical Paper / Technique / dx.doi.org/10.13182/NT77-A31875

Elastic-Plastic Analysis of Pressurized Ducts with Rounded Corners

H. J. Petroski

Nuclear Technology / Volume 35 / Number 3 / October 1977 / Pages 671-676

Technical Note / Reactor / dx.doi.org/10.13182/NT77-A31876