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Volume 7

Number 1 | Number 2 | Number 3 | Number 4 | Number 5 | Number 6

Number 1

Vibration Testing and Earthquake Response of Nuclear Reactors

Craig B. Smith, R. B. Matthiesen

Nuclear Technology / Volume 7 / Number 1 / July 1969 / Pages 6-34

Reactor Siting / dx.doi.org/10.13182/NT69-A28382

Nuclear Reaction Rates in EBR-II Irradiated Stainless Steel

N. D. Dudey, Robert R. Heinrich, J. Williams, Allen A. Madson

Nuclear Technology / Volume 7 / Number 1 / July 1969 / Pages 35-43

Reactor / dx.doi.org/10.13182/NT69-A28383

Enriched-Uranium Production Planning

D. E. Hatch, S. A. Levin

Nuclear Technology / Volume 7 / Number 1 / July 1969 / Pages 44-54

Fuel Cycle / dx.doi.org/10.13182/NT69-A28384

Locating Radioactive Wastes Using Infrared Scanning Techniques

J. D. Jensen

Nuclear Technology / Volume 7 / Number 1 / July 1969 / Pages 55-61

Radioactive Waste / dx.doi.org/10.13182/NT69-A28385

Neutron Emission Rates and Energy Spectra of Two 238Pu Power Sources

M. E. Anderson, R. A. Neff

Nuclear Technology / Volume 7 / Number 1 / July 1969 / Pages 62-66

Radioisotope / dx.doi.org/10.13182/NT69-A28386

Fast-Neutron Effects on Type-304 Stainless Steel

R. Carlander, S. D. Harkness, F. L. Yaggee

Nuclear Technology / Volume 7 / Number 1 / July 1969 / Pages 67-75

Material / dx.doi.org/10.13182/NT69-A28387

Calibration of Electromagnetic Flowmeters in the Enrico Fermi Atomic Power Plant

T. Meshii, J. A. Ford

Nuclear Technology / Volume 7 / Number 1 / July 1969 / Pages 76-83

Instrument / dx.doi.org/10.13182/NT69-A28388

Derivative Neutron Activation Determination of Magnesium

James B. Smathers

Nuclear Technology / Volume 7 / Number 1 / July 1969 / Pages 84-88

Analysis / dx.doi.org/10.13182/NT69-A28389

Calculation of Neutron Fluence-to-Kerma Factors for the Human Body

J. J. Ritts, M. Solomito, P. N. Stevens

Nuclear Technology / Volume 7 / Number 1 / July 1969 / Pages 89-99

Technique / dx.doi.org/10.13182/NT69-A28390

The Laser Microprobe Applied to Investigation of Sodium Penetration into Stainless Steel

Edmund S. Sowa

Nuclear Technology / Volume 7 / Number 1 / July 1969 / Pages 100-105

Technique / dx.doi.org/10.13182/NT69-A28391

A Technique for Demonstrating Cmax of a Plume Using Tritiated Moisture

N. I. Sax, J. C. Daly, J. J. Gabay

Nuclear Technology / Volume 7 / Number 1 / July 1969 / Pages 106-112

Technique / dx.doi.org/10.13182/NT69-A28392

Number 2

Stability Studies of In-Core Thermionic Reactor Concepts

R. L. Brehm, D. L. Hetrick, T. R. Schmidt

Nuclear Technology / Volume 7 / Number 2 / August 1969 / Pages 117-127

Reactor / dx.doi.org/10.13182/NT69-A28355

Measured Thermal-Neutron-Flux Perturbations in Cylinders in a Test Reactor

Nuclear Technology / Volume 7 / Number 2 / August 1969 / Pages 128-138

Reactors / dx.doi.org/10.13182/NT69-A28356

236Pu Contaminant in 238Pu Produced in Power Reactors

S. V. Topp

Nuclear Technology / Volume 7 / Number 2 / August 1969 / Pages 139-143

Economics / dx.doi.org/10.13182/NT69-A28357

The Corrosion and Compatibility of Vanadium Alloys for Fuel-Element Cladding

K. C. Thomas, E. C. Bishop, G. A. Whitlow

Nuclear Technology / Volume 7 / Number 2 / August 1969 / Pages 144-154

Radioisotopes / dx.doi.org/10.13182/NT69-A28358

Zirconium Getiering Effect of Stainless Steel in Sodium

William T. Lee

Nuclear Technology / Volume 7 / Number 2 / August 1969 / Pages 155-163

Radioisotopes / dx.doi.org/10.13182/NT69-A28359

Evaluation of Some Large Area Silicon Junction Detectors for Cryogenic Applications

H. H. Nichols, J. M. Palms

Nuclear Technology / Volume 7 / Number 2 / August 1969 / Pages 164-169

Hot Laboratories / dx.doi.org/10.13182/NT69-A28360

Application of Fission-Fragment Etch-Pit Techniques in Uranium Detection

Nuclear Technology / Volume 7 / Number 2 / August 1969 / Pages 170-178

Accelerators / dx.doi.org/10.13182/NT69-A28361

Epithermal-Neutron Spectrum Determination Using a Plural Foil

A. L. Dekker

Nuclear Technology / Volume 7 / Number 2 / August 1969 / Pages 179-180

Accelerators / dx.doi.org/10.13182/NT69-A28362

Number 3

Nuclear Excavation: Theory and Applications

Joseph B. Knox

Nuclear Technology / Volume 7 / Number 3 / September 1969 / Pages 189-231

Nuclear Explosive / dx.doi.org/10.13182/NT69-A28603

Results of the Cabriolet Excavation Experiment

Howard A. Tewes

Nuclear Technology / Volume 7 / Number 3 / September 1969 / Pages 232-242

Nuclear Explosive / dx.doi.org/10.13182/NT69-A28604

Project Buggy: A Nuclear Row-Excavation Experiment

John Toman

Nuclear Technology / Volume 7 / Number 3 / September 1969 / Pages 243-252

Nuclear Explosive / dx.doi.org/10.13182/NT69-A28605

The Corps of Engineers Nuclear Construction Research Program

Walter C. Day

Nuclear Technology / Volume 7 / Number 3 / September 1969 / Pages 253-268

Nuclear Explosive / dx.doi.org/10.13182/NT69-A28606

Ten Years of High Explosive Cratering Research at Sandia Laboratory

Luke J. Vortman

Nuclear Technology / Volume 7 / Number 3 / September 1969 / Pages 269-304

Nuclear Explosive / dx.doi.org/10.13182/NT69-A28607

Nuclear Excavation Design af a Transisthmian Sea-Level Canal

Lieutenant Colonel Bernard C. Hughes

Nuclear Technology / Volume 7 / Number 3 / September 1969 / Pages 305-327

Nuclear Explosive / dx.doi.org/10.13182/NT69-A28608

Number 4

Fuel Handling System For Core Elements Of a Pebble-Bed Reactor

U. Hennings

Nuclear Technology / Volume 7 / Number 4 / October 1969 / Pages 334-341

Reactor / dx.doi.org/10.13182/NT69-A28475

Computer-Aided Calibration of a Fine Autorod

Charles E. Cohn, Ratib A. Karam, James E. Marshall, Jacob M. Van Doorninck

Nuclear Technology / Volume 7 / Number 4 / October 1969 / Pages 342-346

Reactor / dx.doi.org/10.13182/NT69-A28476

In-Core Study of the Mechanical Interaction between Fuel and Cladding

G. Kjaerheim, E. Rolstad

Nuclear Technology / Volume 7 / Number 4 / October 1969 / Pages 347-360

Fuel / dx.doi.org/10.13182/NT69-A28477

Deposition of Iodine on Low Chromium-Alloy Steel

Clyde E. Milstead, Wayne E. Bell, J. H. Norman

Nuclear Technology / Volume 7 / Number 4 / October 1969 / Pages 361-366

Material / dx.doi.org/10.13182/NT69-A28478

An Approach to the Design of a Multifuel-Capsule Radioisotope Thermoelectric Generator

Frederick A. Schumann

Nuclear Technology / Volume 7 / Number 4 / October 1969 / Pages 367-373

Radioisotope / dx.doi.org/10.13182/NT69-A28479

Sensitive, Fast Response Reactor Coolant Impurity Measurement Instrument

T. Roger Billeter, R. R. Schemmel

Nuclear Technology / Volume 7 / Number 4 / October 1969 / Pages 374-382

Instrument / dx.doi.org/10.13182/NT69-A28480

Determination of 16O in Microcrystalline Carbon by Indirect Neutron Activation Analysis

James S. Mattson, John C. Crittenden, Harry B. Mark, Jr.

Nuclear Technology / Volume 7 / Number 4 / October 1969 / Pages 383-384

Analysis / dx.doi.org/10.13182/NT69-A28481

Deuterium Analysis by Photoneutron Detection

Kenneth D. George, Henry H. Kramer

Nuclear Technology / Volume 7 / Number 4 / October 1969 / Pages 385-388

Analysis / dx.doi.org/10.13182/NT69-A28482

Applications of Neutron-Activation Analysis to the Measurement of the Evaporation Rate of Solids in the Range of 10-7 to 10-9 g/(cm2 sec)

I. A. Maslov, V. A. Lucknitsky, N. M. Karnaukhova, G. I. Karaganova

Nuclear Technology / Volume 7 / Number 4 / October 1969 / Pages 389-392

Analysis / dx.doi.org/10.13182/NT69-A28483

The Use of 184W as a Thermal Flux Monitor at High Temperatures

Lauren L. Ball, Paul J. Richardson, Dean W. Sheibley

Nuclear Technology / Volume 7 / Number 4 / October 1969 / Pages 393-396

Techniques / dx.doi.org/10.13182/NT69-A28484

Number 5

Critical Mass of a Water-Reflected Plutonium Sphere

David R. Smith, William U. Geer

Nuclear Technology / Volume 7 / Number 5 / November 1969 / Pages 405-408

Reactor / dx.doi.org/10.13182/NT69-A28442

Dosimetric Intercomparison Measurements in the Core of Reactor ISIS at Saclay

B. Radak, O. Gal, V. Marković, Lj. Petković, Boris Kidrič Institute of Nuclear Sciences, Vinča, Yugoslavia, M. Labrousse, J. Libmann, J. Roger

Nuclear Technology / Volume 7 / Number 5 / November 1969 / Pages 409-414

Reactor / dx.doi.org/10.13182/NT69-A28443

Undersea Reactor Siting

Robert N. Endebrock, Walter H. D'Ardenne, Warren F. Witzig

Nuclear Technology / Volume 7 / Number 5 / November 1969 / Pages 415-424

Reactors Siting / dx.doi.org/10.13182/NT69-A28444

Fluidized-Bed Fluorination of UO2-PuO2-Fission Product Pellets with Brf5 and Fluorine. Part I: The Fluorination of Uranium, Neptunium, and Plutonium

L. J. Anastasia, P. G. Alfredson, M. J. Steindler

Nuclear Technology / Volume 7 / Number 5 / November 1969 / Pages 425-432

Chemical Process / dx.doi.org/10.13182/NT69-A28445

Fluidized-Bed Fluorination of UO2-PUO2-Fission Product Pellets with BrF5 and Fluorine. Part II: Process Considerations

L. J. Anastasia, P. G. Alfredson, M. J. Steindler

Nuclear Technology / Volume 7 / Number 5 / November 1969 / Pages 433-442

Chemical Process / dx.doi.org/10.13182/NT69-A28446

Vanadium Alloys vs Stainless Steel for Sodium-Cooled Fast Reactor Cladding

G. Edison, G. A. Whitlow

Nuclear Technology / Volume 7 / Number 5 / November 1969 / Pages 443-455

Fuel / dx.doi.org/10.13182/NT69-A28447

Incremental Cost Considerations Related to Production of Enriched Uranium

A. de la Garza, S. A. Levin

Nuclear Technology / Volume 7 / Number 5 / November 1969 / Pages 456-465

Economic / dx.doi.org/10.13182/NT69-A28448

Characteristics of an “On-Stream” Analysis System Using a Multikilocurie 124Sb-Be Neutron Source

W. E. Downs, M. W. Davis

Nuclear Technology / Volume 7 / Number 5 / November 1969 / Pages 466-471

Instrument / dx.doi.org/10.13182/NT69-A28449

The Radiation-Induced Graft Polymerization of Methyl Methacrylate and Cellulose

Carl A. Detrick, James L. Kelly

Nuclear Technology / Volume 7 / Number 5 / November 1969 / Pages 472-477

Radiation / dx.doi.org/10.13182/NT69-A28450

Neutron Activation Analysis of the Selenium Content of Fossil Fuels

K. K. S. Pillay, C. C. Thomas, Jr., J. W. Kaminski

Nuclear Technology / Volume 7 / Number 5 / November 1969 / Pages 478-483

Analysis / dx.doi.org/10.13182/NT69-A28451

Number 6

Comparison of Measured and Calculated Uranium Reaction Rates in a Steam-Cooled Fast Assembly in Sneak

R. Böhme, H. Seufert

Nuclear Technology / Volume 7 / Number 6 / December 1969 / Pages 494-504

Reactor / dx.doi.org/10.13182/NT69-A28368

The Criticality of a Uranium-Solution Slab under Various Reflector Conditions

Robert E. Rothe, C. L. Schuske, E. E. Hicks

Nuclear Technology / Volume 7 / Number 6 / December 1969 / Pages 505-512

Reactor / dx.doi.org/10.13182/NT69-A28369

The Polarity Correlation of Reactor Noise in the Frequency Domain

W. Seifritz

Nuclear Technology / Volume 7 / Number 6 / December 1969 / Pages 513-522

Reactor / dx.doi.org/10.13182/NT69-A28370

A Practical Approach to Nuclear Criticality Safety

William Bradley Lewis

Nuclear Technology / Volume 7 / Number 6 / December 1969 / Pages 523-528

Reactor Siting / dx.doi.org/10.13182/NT69-A28371

Simultaneous Electrolytic Cutting and Lixiviation Head-End Process Step for Nuclear Fuel Reprocessing

J. Van Impe, J. P. Rombaux, P. Chaussonnet

Nuclear Technology / Volume 7 / Number 6 / December 1969 / Pages 529-536

Fuel / dx.doi.org/10.13182/NT69-A28372

Models for Fission-Gas Release from Pyrocarbon-Coated Particles

C. D. Baumann, P. E. Reagan

Nuclear Technology / Volume 7 / Number 6 / December 1969 / Pages 537-549

Fuel / dx.doi.org/10.13182/NT69-A28373

In-Pile Fuel Studies for Design Purposes

G. Testa, F. Doria, P. Grillo, A. Nobili, P. L. Rotoloni

Nuclear Technology / Volume 7 / Number 6 / December 1969 / Pages 550-560

Fuel / dx.doi.org/10.13182/NT69-A28374

Damage Functions and Data Correlation

W. N. Mcelroy, R. E. Dahl, Jr.

Nuclear Technology / Volume 7 / Number 6 / December 1969 / Pages 561-571

Material / dx.doi.org/10.13182/NT69-A28375

Prediction of Failure Times for Decay-Heated Capsules Containing Alpha-Emitting Isotopes

R. L. Stephenson, R. W. Swindeman

Nuclear Technology / Volume 7 / Number 6 / December 1969 / Pages 572-575

Radioisotope / dx.doi.org/10.13182/NT69-A28376

Distribution of Neutrons from a 252Cf Source in Soil At Depth and Just Below the Air-Ground Interface

F. E. Senftle, P. W. Philbin, P. Sarigianis

Nuclear Technology / Volume 7 / Number 6 / December 1969 / Pages 576-583

Radioisotope / dx.doi.org/10.13182/NT69-A28377

A Variable-Spacing, Vacuum-Type Thermionic Diode

George H. Miley, C. Forbes Dewey, Jr.

Nuclear Technology / Volume 7 / Number 6 / December 1969 / Pages 584-598

Radioisotope / Education / dx.doi.org/10.13182/NT69-A28378