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Volume 10

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Number 1

The SEFOR Minimum Critical Core

L. D. Noble, P. Greebler, G. R. Pflasterer, Jr., B. U. B. Sarma, D. Wintzer

Nuclear Technology / Volume 10 / Number 1 / January 1971 / Pages 5-10

Technical Paper and Note / Reactor / dx.doi.org/10.13182/NT71-A30941

Fission Products in Reactor Dynamics

Jan S. Woyski

Nuclear Technology / Volume 10 / Number 1 / January 1971 / Pages 11-16

Technical Paper and Note / Reactor / dx.doi.org/10.13182/NT71-A30942

The Effect of a Metallurgical Phase Change in Fuel on the Power Coefficient of EBR-II

John K. Long

Nuclear Technology / Volume 10 / Number 1 / January 1971 / Pages 17-21

Technical Paper and Note / Reactor / dx.doi.org/10.13182/NT71-A30943

A Proposal for Using Nuclear Reactors as Thermal Radiation Sources

K. Almenas

Nuclear Technology / Volume 10 / Number 1 / January 1971 / Pages 22-32

Technical Paper and Note / Reactor / dx.doi.org/10.13182/NT71-A30944

On-Line Noble Gas Fission Product Monitoring in Experimental Breeder Reactor II

G. S. Brunson

Nuclear Technology / Volume 10 / Number 1 / January 1971 / Pages 33-43

Technical Paper and Note / Reactor / dx.doi.org/10.13182/NT71-A30945

Prediction of the Irradiation Performance of. Coated Particle Fuels by Means of Stress-Analysis Models

J. L. Kaae, D. W. Stevens, C. S. Luby

Nuclear Technology / Volume 10 / Number 1 / January 1971 / Pages 44-53

Technical Paper and Note / Fuel / dx.doi.org/10.13182/NT71-A30946

Thermal Expansion of Uranium and Tantalum Monocarbides up to 2700°C

Hans K. Richards

Nuclear Technology / Volume 10 / Number 1 / January 1971 / Pages 54-61

Technical Paper and Note / Fuel / dx.doi.org/10.13182/NT71-A30947

Development of an Ultrafine Grain Size Type-316 Stainless-Steel Cladding

G. A. Reimann

Nuclear Technology / Volume 10 / Number 1 / January 1971 / Pages 62-66

Technical Paper and Note / Fuel / dx.doi.org/10.13182/NT71-A30948

Analysis of Corrosion of Stainless Steel in a Sodium and High Radiation Environment

J. N. Anno, J. A. Walowit

Nuclear Technology / Volume 10 / Number 1 / January 1971 / Pages 67-75

Technical Paper and Note / Material / dx.doi.org/10.13182/NT71-A30949

Ionizing Radiation Effects in Lithium Niobate

William Primak, T. T. Anderson, S. L. Halverson

Nuclear Technology / Volume 10 / Number 1 / January 1971 / Pages 76-84

Technical Paper and Note / Radiation / dx.doi.org/10.13182/NT71-A30950

A Dual Spectrum Concept for LMFBR Fuel Assay

Charles Kelber

Nuclear Technology / Volume 10 / Number 1 / January 1971 / Pages 85-90

Technical Paper and Note / Technique / dx.doi.org/10.13182/NT71-A30951

Number 2

Experiences with Dynamic Testing Methods at the Molten-Salt Reactor Experiment

T. W. Kerlin, S. J. Ball, R. C. Steffy, M. R. Buckner

Nuclear Technology / Volume 10 / Number 2 / February 1971 / Pages 103-117

Technical Paper and Note / Reactor / dx.doi.org/10.13182/NT71-A30919

Theoretical Dynamics Analysis of the Molten-Salt Reactor Experiment

T. W. Kerlin, S. J. Ball, R. C. Steffy

Nuclear Technology / Volume 10 / Number 2 / February 1971 / Pages 118-132

Technical Paper and Note / Reactor / dx.doi.org/10.13182/NT71-A30920

A Small Nuclear Reactor for Undersea Use

Carroll B. Mills

Nuclear Technology / Volume 10 / Number 2 / February 1971 / Pages 133-138

Technical Paper and Note / Reactor / dx.doi.org/10.13182/NT71-A30921

The Instrumented Subassembly System in Ebr-II

A. Smaardyk, C. J. Divona, E. Hutter

Nuclear Technology / Volume 10 / Number 2 / February 1971 / Pages 139-159

Technical Paper and Note / Reactor / dx.doi.org/10.13182/NT71-A30922

Calculation of Neutron Detector Response in a Subcritical Reactor

W. R. Waltz, J. F. Walter

Nuclear Technology / Volume 10 / Number 2 / February 1971 / Pages 160-167

Technical Paper and Note / Reactor / dx.doi.org/10.13182/NT71-A30923

Short-Interval Series Pulsing—Experimental Studies and Numerical Experiments

H. A. Kurstedt, Jr., G. H. Miley

Nuclear Technology / Volume 10 / Number 2 / February 1971 / Pages 168-178

Technical Paper and Note / Reactor / dx.doi.org/10.13182/NT71-A30924

An Empirical Model for Safe Pipe Intersections Containing Fissile Solution

Deanne Dickinson, C. L. Schuske

Nuclear Technology / Volume 10 / Number 2 / February 1971 / Pages 179-187

Technical Paper and Note / Chemical Processing / dx.doi.org/10.13182/NT71-A30925

Very Intense Neutron Source

R. M. Brugger, G. J. Russell, B. W. Johnson, G. P. DeVault†

Nuclear Technology / Volume 10 / Number 2 / February 1971 / Pages 188-203

Technical Paper and Note / Accelerator / dx.doi.org/10.13182/NT71-A30926

Construction Materials for Neutron Capture-Gamma-Ray Measurement Assembly Using Californium-252

F. E. Senftle, A. G. Evans, D. Duffey, P. F. Wiggins

Nuclear Technology / Volume 10 / Number 2 / February 1971 / Pages 204-210

Technical Paper and Note / Instrument / dx.doi.org/10.13182/NT71-A30927

Detection and Location of Leaking Triga Reactor Fuel Elements

G. D. Bouchey, S. J. Gage

Nuclear Technology / Volume 10 / Number 2 / February 1971 / Pages 211-214

Technical Paper and Note / Instrument / dx.doi.org/10.13182/NT71-A30928

A Simple Total-Reflecting Low-Energy Neutron Spectrometer

Werner Fiala, Carlos V. Wheeler

Nuclear Technology / Volume 10 / Number 2 / February 1971 / Pages 215-220

Technical Paper and Note / Instrument / dx.doi.org/10.13182/NT71-A30929

Self-Auditing Multichannel Neutron Monitor

W. F. Splichal, Jr.

Nuclear Technology / Volume 10 / Number 2 / February 1971 / Pages 221-223

Technical Paper and Note / Instrument / dx.doi.org/10.13182/NT71-A30930

Neutron Activation Analysis of Inorganic Constituents of Airborne Particulates

K. K. S. Pillay, C. C. Thomas, Jr., C. M. Hyche

Nuclear Technology / Volume 10 / Number 2 / February 1971 / Pages 224-231

Technical Paper and Note / Analysis / dx.doi.org/10.13182/NT71-A30931

Formation of Intimate Oxide-Carbon Mixtures of Fuel Materials as an Intermediate for Carbide and Nitride Fuels

E. A. Coppinger, B. M. Johnson

Nuclear Technology / Volume 10 / Number 2 / February 1971 / Pages 232-236

Technical Paper and Note / Chemical Processing / dx.doi.org/10.13182/NT71-A30932

Number 3

A Fast Reactor Assessment Study

Reino Ekholm

Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 249-256

Technical Paper / Reactor / dx.doi.org/10.13182/NT71-A30957

Prediction of Three-Dimensional Core Performance of JPDR (A BWR) for Burnup Cases

T. Shimooke

Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 257-272

Technical Paper / Reactor / dx.doi.org/10.13182/NT71-A30958

Experience in Reactor Malfunction Diagnosis Using On-Line Noise Analysis

D. N. Fry

Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 273-282

Technical Paper / Reactor / dx.doi.org/10.13182/NT71-A30959

Preparation of Sol-Gel Spheres Smaller than 200 Microns without Fluidization

P. A. Haas

Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 283-292

Technical Paper / Fuel / dx.doi.org/10.13182/NT71-A30960

A Study of Noncondensable Effects in a Heat Pipe

G. T. Colwell, C. L. Williams, J. C. Hsu, G. E. Zevallos

Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 293-300

Technical Paper / Fuel / dx.doi.org/10.13182/NT71-A30961

An Explicit Solution for Stresses in Pyrocarbon-Coated Fuel Particles

D. W. Stevens

Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 301-306

Technical Paper / Fuel / dx.doi.org/10.13182/NT71-A30962

Carbon Transport in Flowing Sodium

Prodyot Roy, Gary P. Wozadlo

Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 307-314

Technical Paper / Material / dx.doi.org/10.13182/NT71-A30963

Generation of a Low-Energy Positron Beam

Günter H. Lohnert, Richard T. Schneider

Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 315-321

Technical Paper / Radioisotope / dx.doi.org/10.13182/NT71-A30964

The Preparation and Properties of LiPb, a Novel Material for Shields and Collimators

Norman A. Frigerio, Leo L. LaVoy

Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 322-324

Technical Paper / Shielding / dx.doi.org/10.13182/NT71-A30965

Bremsstrahlung Shielding from Electron Trapping in Dielectrics

D. L. Hollis

Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 325-327

Technical Paper / Shielding / dx.doi.org/10.13182/NT71-A30966

Corrections for Dead-Time Losses in the Measurement of Gamma-Ray Spectra of Short-Lived Radionuclides

H. A. Das, J. Zonderhuis

Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 328-334

Technical Paper / Instrument / dx.doi.org/10.13182/NT71-A30967

An Electrochemical Carbon Meter for Use in Sodium

F. J. Salzano, L. Newman, M. R. Hobdell

Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 335-347

Technical Paper / Instrument / dx.doi.org/10.13182/NT71-A30968

Prediction of Nuclear Weapon Neutron-Radiation Environments

R. L. French, L. G. Mooney

Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 348-365

Technical Paper / Radiation / dx.doi.org/10.13182/NT71-A30969

A Multi-Spectra Neutron Irradiation Technique for the Nondestructive Assay of Fissionable Materials

H. O. Menlove, R. H. Augustson, Darryl B. Smith

Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 366-379

Technical Paper / Analysis / dx.doi.org/10.13182/NT71-A30970

Use of Simulation Plus Real Steam Turbine for Teaching Theory and Operation of a Pressurized Water Reactor

M. A. Schultz, Wayne F. Eckley

Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 380-390

Technical Paper / Education / dx.doi.org/10.13182/NT71-A30971

A Technical Note on D-T Fusion Reactor Afterheat

Donald J. Dudziak

Nuclear Technology / Volume 10 / Number 3 / March 1971 / Pages 391-392

Technical Note / Reactor / dx.doi.org/10.13182/NT71-A30972

Number 4

  • Table of Contents
  • Authors(Thomas H. Row, J. L. Gallagher, L. D. Green, R. T. Marchese, W. F. Pasedag, J. L. Gallagher, W. D. Fletcher, M. J. Bell, R. T. Marchese, J. L. Gallagher, D. D. Malinowski, L. F. Picone, H. E. Zittel, T. H. Row, W. E. Joyce, W. N. Bishop, D. A. Nitti, D. W. LaBelle, B. A. Soldano, W. T. Ward, L. Devell, R. Hesböl, E. Bachofner, L. F. Parsly, Y. Nishizawa, S. Oshima, T. Maekawa, R. K. Hilliard, A. K. Postma, J. D. McCormack, L. F. Coleman, B. Guerrini, S. Lanza, M. Mazzini, R. Mirandola, C. D. Watson, J. C. Griess, T. H. Row, G. A. West, J. C. Griess, A. L. Bacarella)
  • Corrigendum
  • Preface: Symposium on Reactor Containment Spray System Technology(Thomas H. Row)

Design of Spray Additive Systems

J. L. Gallagher, L. D. Green, R. T. Marchese

Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 406-411

Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16249

Drop Size Distribution and Spray Effectiveness

W. F. Pasedag, J. L. Gallagher

Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 412-419

Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16250

Post-LOCA Hydrogen Generation in PWR Containments

W. D. Fletcher, M. J. Bell, R. T. Marchese, J. L. Gallagher

Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 420-427

Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16251

Iodine Removal in the Ice Condenser System

D. D. Malinowski, L. F. Picone

Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 428-435

Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16252

Radiation and Thermal Stability of Spray Solutions

H. E. Zittel, T. H. Row

Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 436-443

Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16253

Sodium Thiosulfate Spray System for Radioiodine Removal

W. E. Joyce*

Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 444-448

Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16254

Stability of Thiosulfate Spray Solutions

W. N. Bishop, D. A. Nitti

Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 449-453

Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16255

Post-Accident Hydrogen Generation and Control

D. W. LaBelle

Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 454-459

Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16256

A Study of the Absorption of CH3I by Aqueous Spray Solutions

B. A. Soldano, W. T. Ward

Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 460-465

Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16257

Studies on Iodine Trapping by Water Systems at Studsvik

L. Devell, R. Hesböl, E. Bachofner*

Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 466-471

Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16258

Spray Program at the Nuclear Safety Pilot Plant

L. F. Parsly

Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 472-485

Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16259

Removal of Iodine from Atmosphere by Sprays

Y. Nishizawa, S. Oshima, T. Maekawa

Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 486-498

Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16260

Removal of Iodine and Particles by Sprays in the Containment Systems Experiment

R. K. Hilliard, A. K. Postma, J. D. McCormack,*, L. F. Coleman**

Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 499-519

Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16261

Scalbatraio Center for Research in Nuclear Safety

B. Guerrini, S. Lanza, M. Mazzini, R. Mirandola

Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 520-537

Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16262

Protective Coatings (Paints) for PWR and BWR Reactor Containment Facilities

C. D. Watson, J. C. Griess, T. H. Row, G. A. West

Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 538-545

Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16263

The Corrosion of Materials in Reactor Containment Spray Solutions

J. C. Griess, A. L. Bacarella

Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 546-553

Technical Paper / Symposium on Reactor Containment Spray System Technology / Reactor / dx.doi.org/10.13182/NT71-A16264

Nuclear Energy Costs and Economic Development, Proceedings of a Symposium in Istanbul, October 1969

Pablo Mulás del Pozo

Nuclear Technology / Volume 10 / Number 4 / April 1971 / Pages 554-555

Department / Symposium on Reactor Containment Spray System Technology / Book Review / dx.doi.org/10.13182/NT71-A16265

Random Noise Techniques in Nuclear Reactor Systems

Lynn Weaver

Nuclear Technology / Volume 10 / Number 4 / April 1971 / Page 555

Department / Symposium on Reactor Containment Spray System Technology / Book Review / dx.doi.org/10.13182/NT71-A16266