Home / Publications / Journals / Nuclear Technology / Volume 8

Volume 8

Number 1

Table of Contents
Scientific and Technical Communication, A Pressing National Problem and Recommendations for Its Solution(Margaret Butler)
Sources of Tritium and Its Behavior upon Release to the Environment(Benjamin M. Ma)
Engineer's Guide to High-Temperature Materials(Monte V. Davis)

A Flow Experiment on a Curved-Porous-Wall Gas-Core Reactor Geometry

Chester D. Lanzo

Nuclear Technology / Volume 8 / Number 1 / January 1970 / Pages 6-12

Reactor / dx.doi.org/10.13182/NT70-A28628

Pilot Plant Studies of Methyl Iodide Cleanup by Sprays

L. F. Parsly

Nuclear Technology / Volume 8 / Number 1 / January 1970 / Pages 13-22

Chemical Processing / dx.doi.org/10.13182/NT70-A28629

Porous UO₂ Bodies Produced by Reduction of U₃O₈

T. N. Washburn

Nuclear Technology / Volume 8 / Number 1 / January 1970 / Pages 23-28

Fuel / dx.doi.org/10.13182/NT70-A28630

Refluxing Capsule Experiments with Refractory Metals and Boiling Alkali Metals

J. R. DiStefano, J. H. Devan

Nuclear Technology / Volume 8 / Number 1 / January 1970 / Pages 29-44

Fuel / dx.doi.org/10.13182/NT70-A28631

Economics of Desalting Water and Generating Electricity in Singapore

William R. Bohl, Jerry L. Gillette, Max W. Carbon

Nuclear Technology / Volume 8 / Number 1 / January 1970 / Pages 45-51

Economic / dx.doi.org/10.13182/NT70-A28632

The Interaction of Tellurium Dioxide and Water Vapor

A. P. Malinauskas, J. W. Gooch, Jr., J. D. Redman

Nuclear Technology / Volume 8 / Number 1 / January 1970 / Pages 52-57

Material / dx.doi.org/10.13182/NT70-A28633

The Dissolution of Metal Corrosion Products in Deionized Water at 38° C (100° F)

Barbara A. Johnson

Nuclear Technology / Volume 8 / Number 1 / January 1970 / Pages 58-61

Material / dx.doi.org/10.13182/NT70-A28634

Cesium Purification by Zeolite Ion Exchange

B. W. Mercer, L. L. Ames, P. W. Smith

Nuclear Technology / Volume 8 / Number 1 / January 1970 / Pages 62-69

Radioisotope / dx.doi.org/10.13182/NT70-A28635

Alpha Monitor for Rapid Contamination Screening of Hands and Shoes

W. F. Splichal, Jr.

Nuclear Technology / Volume 8 / Number 1 / January 1970 / Pages 70-72

Radiation / dx.doi.org/10.13182/NT70-A28636

Applications of Rare Earth Tracers to Gunpowder Residues

K. K. S. Pillay, C. C. Thomas, Jr., D. M. Hart, D. Didising, R. C. Thomas

Nuclear Technology / Volume 8 / Number 1 / January 1970 / Pages 73-78

Analysis / dx.doi.org/10.13182/NT70-A28637

Nondestructive Assay of Fissionable Materials

D. W. Jones, P. R. Malmberg, T. H. May, C. V. Strain

Nuclear Technology / Volume 8 / Number 1 / January 1970 / Pages 79-83

Analysis / dx.doi.org/10.13182/NT70-A28638

Pulse Rate Correlation in Dynamic Experiments

Rocco A. Fazzolare

Nuclear Technology / Volume 8 / Number 1 / January 1970 / Pages 84-87

Technique / dx.doi.org/10.13182/NT70-A28639

On the Gamma-Ray One-Shot-Collimator Measurement of Two-Phase-Flow Void Fractions

R. P. Gardner, R. H. Bean, J. K. Ferrell

Nuclear Technology / Volume 8 / Number 1 / January 1970 / Pages 88-94

Technique / dx.doi.org/10.13182/NT70-A28640

A Convenient Technique for Techniques Stirring Liquid Sodium

M. R. Hobdell, F. J. Salzano

Nuclear Technology / Volume 8 / Number 1 / January 1970 / Pages 95-96

Technique / dx.doi.org/10.13182/NT70-A28641

Number 2

Molten-Salt Reactors—History, Status, and Potential

M. W. Rosenthal, P. R. Kasten, R. B. Briggs

Nuclear Technology / Volume 8 / Number 2 / February 1970 / Pages 107-117

Reactor / dx.doi.org/10.13182/NT70-A28619

Experience with the Molten-Salt Reactor Experiment

Paul N. Haubenreich, J. R. Engel

Nuclear Technology / Volume 8 / Number 2 / February 1970 / Pages 118-136

Reactor / dx.doi.org/10.13182/NT8-2-118

Molten-Salt Reactor Chemistry

W. R. Grimes

Nuclear Technology / Volume 8 / Number 2 / February 1970 / Pages 137-155

Reactor / dx.doi.org/10.13182/NT70-A28621

New Developments in Materials for Molten-Salt Reactors

H. E. McCoy, R. L. Beatty, W. H. Cook, R. E. Gehlbach C. R. Kennedy, J. W. Koger, A. P. Litman, C. E. Sessions, J. R. Weir

Nuclear Technology / Volume 8 / Number 2 / February 1970 / Pages 156-169

Reactor / dx.doi.org/10.13182/NT70-A28622

Engineering Development of the MSBR Fuel Recycle

M. E. Whatley, L. E. McNeese, W. L. Carter, L. M. Ferris, E. L. Nicholson

Nuclear Technology / Volume 8 / Number 2 / February 1970 / Pages 170-178

Reactor / dx.doi.org/10.13182/NT70-A28623

Graphite and Xenon Behavior and their Influence on Molten-Salt Reactor Design

Dunlap Scott, W. P. Eatherly

Nuclear Technology / Volume 8 / Number 2 / February 1970 / Pages 179-189

Reactor / dx.doi.org/10.13182/NT70-A28624

The Design and Performance Features of a Single-Fluid Molten-Salt Breeder Reactor

E. S. Bettis, Roy C. Robertson

Nuclear Technology / Volume 8 / Number 2 / February 1970 / Pages 190-207

Reactor / dx.doi.org/10.13182/NT70-A28625

Reactor Physics and Fuel-Cycle Analyses

A. M. Perry, H. F. Bauman

Nuclear Technology / Volume 8 / Number 2 / February 1970 / Pages 208-219

Reactor / dx.doi.org/10.13182/NT70-A28626

Number 3

Table of Contents
Characteristics of a Continuous “On-Stream” Analysis System Using a Multikilocurie ¹²⁴Sb_Be Neutron Source
A Practical Approach to Nuclear Criticality Safety
Lanthanide / Actinide Chemistry(Burris B. Cunningham)
Molecular Processes on Solid Surfaces(Donald E. O'Reilly)
Statistical Models in Engineering(Neil Cox)

Measurement of Control Schemes for Fast-Spectrum Compact Reactors

J. F. Kunze, F. L. Sims, J. M. Byrne, R. E. Reid

Nuclear Technology / Volume 8 / Number 3 / March 1970 / Pages 226-239

Paper / Reactor / dx.doi.org/10.13182/NT70-A28669

N-Reactor-WPPSS Complex Operating Performance

Emil E. Leitz

Nuclear Technology / Volume 8 / Number 3 / March 1970 / Pages 240-245

Paper / Reactor / dx.doi.org/10.13182/NT70-A28670

The Measurement of Radial Power Distributions in a Triga Fuel Element during Reactor Power Excursions

W. A. Goodwin, M. E. Wyman

Nuclear Technology / Volume 8 / Number 3 / March 1970 / Pages 246-254

Paper / Reactor / dx.doi.org/10.13182/NT70-A28671

An Experimental Analysis Of Fission-Gas Holdup Beds

Dwight W. Underhill

Nuclear Technology / Volume 8 / Number 3 / March 1970 / Pages 255-260

Paper / Fuel / dx.doi.org/10.13182/NT70-A28672

Stationary Gas Bubbles in Narrow Liquid-Filled Gaps

H. O. Schad, A. A. Bishop

Nuclear Technology / Volume 8 / Number 3 / March 1970 / Pages 261-275

Paper / Fuel / dx.doi.org/10.13182/NT70-A28673

Well-Logging Research for Geonuclear Technology

J. R. Hearst, R. C. Carlson

Nuclear Technology / Volume 8 / Number 3 / March 1970 / Pages 276-282

Paper / Nuclear Explosive / dx.doi.org/10.13182/NT70-A28674

Void-Space Analysis by Use of Thermal-Neutron Analysis Irradiated Air (⁴¹Ar)

Jerry B. F. Champlin

Nuclear Technology / Volume 8 / Number 3 / March 1970 / Pages 283-289

Paper / Analysis / dx.doi.org/10.13182/NT70-A28675

Application of Neutron Activation Analysis to the Sweat Test Diagnosis of Cystic Fibrosis

Robert G. McAndrew, James B. Smathers, , Richard E. Wainerdi, G. M. Harrison, Robert Doggett

Nuclear Technology / Volume 8 / Number 3 / March 1970 / Pages 290-295

Paper / Analysis / dx.doi.org/10.13182/NT70-A28676

Experimental Determination of the Differential Fast-Neutron Flux in the High Flux Isotope Reactor Using Techniques Threshold Detectors

H. L. Dodds, Jr., P. F. Pasqua

Nuclear Technology / Volume 8 / Number 3 / March 1970 / Pages 296-301

Paper / Technique / dx.doi.org/10.13182/NT70-A28677

Reactor Neutron Measurements with Fission Foil-Lexan Detectors

P. F. Rago, N. Goldstein, E. Tochilin

Nuclear Technology / Volume 8 / Number 3 / March 1970 / Pages 302-309

Paper / Technique / dx.doi.org/10.13182/NT70-A28678

The Iodine Collection Efficiency of Activated Charcoal from Hanford Reactor Confinement Systems

J.D. Ludwick

Nuclear Technology / Volume 8 / Number 3 / March 1970 / Pages 310-313

Note / Chemical Processing / dx.doi.org/10.13182/NT70-A28679

Replacement Hafnium Control Rods for the Bonus Reactor

G. M. Tolson, G. R. Davis

Nuclear Technology / Volume 8 / Number 3 / March 1970 / Pages 314-320

Note / Material / dx.doi.org/10.13182/NT70-A28680

Number 4

Accuracy of Power-Distribution Calculation Methods for Uranium and Plutonium Lattices

A. Ariemma, G. Lesnoni La Parola, M. Paoletti Gualandi, P. Peroni, B. Zaffiro

Nuclear Technology / Volume 8 / Number 4 / April 1970 / Pages 328-354

Reactor / dx.doi.org/10.13182/NT70-A28661

A Gaseous-Core Reactor Concept for Electrical Power Generation

Eugene C. Gritton, Benjamin Pinkel

Nuclear Technology / Volume 8 / Number 4 / April 1970 / Pages 355-370

Reactor / dx.doi.org/10.13182/NT70-A28662

Processing of Highly Irradiated Al-Pu Alloy

R. Berger, G. Koehly, C. Musikas, R. Pottier, R. Sontag

Nuclear Technology / Volume 8 / Number 4 / April 1970 / Pages 371-379

Chemical Processing / dx.doi.org/10.13182/NT70-A28663

A Dislocation Etch for Uranium Dioxide

Michael F. Ehman, J. W. Faust, Jr.

Nuclear Technology / Volume 8 / Number 4 / April 1970 / Pages 380-383

Fuel / dx.doi.org/10.13182/NT70-A28664

Capacity Expansion Optimization in a Growing Nuclear Fuel Fabrication Industry

F. J. Homan, T. N. Washburn

Nuclear Technology / Volume 8 / Number 4 / April 1970 / Pages 384-394

Economic / dx.doi.org/10.13182/NT70-A28665

Number 5

Table of Contents

Time-Optimal Digital Control of Zero-Power Nuclear Reactors

Thomas J. Marciniak

Nuclear Technology / Volume 8 / Number 5 / May 1970 / Pages 401-416

Paper / Reactor / dx.doi.org/10.13182/NT70-A28685

Irradiation Performance of Pyrolytic-Carbon- and Silicon-Carbide-Coated Fuel Particles

P. E. Reagan, E. L. Long, Jr., J. G. Morgan, J. H. Coobs

Nuclear Technology / Volume 8 / Number 5 / May 1970 / Pages 417-431

Paper / Fuel / dx.doi.org/10.13182/NT70-A28686

Design and Tests of Null-balanced Fission Gas Pressure Transducer and Controller

John R. Folkrod

Nuclear Technology / Volume 8 / Number 5 / May 1970 / Pages 432-436

Paper / Fuel / dx.doi.org/10.13182/NT70-A28687

The Economics of Blending and Diffusion in Uranium Recycle

A. MacCragh

Nuclear Technology / Volume 8 / Number 5 / May 1970 / Pages 437-444

Paper / Economic / dx.doi.org/10.13182/NT70-A28688

Engineering Design of an Instrumented Pilot Plant for Remote Reactions-Radiation-Induced Polymerization

F. T. Osborne, S. Omi, V. T. Stannett, E. P. Stahel

Nuclear Technology / Volume 8 / Number 5 / May 1970 / Pages 445-449

Paper / Radioisotopes / dx.doi.org/10.13182/NT70-A28689

Dose Rates in a Slab Phantom from Monoenergetic Gamma Rays

H. C. Claiborne, D. K. Trubey

Nuclear Technology / Volume 8 / Number 5 / May 1970 / Pages 450-455

Paper / Shielding / dx.doi.org/10.13182/NT70-A28690

Factors Involved in On-Stream Trace Activation Analysis

H. Al-Shahristani, R. E. Jervis

Nuclear Technology / Volume 8 / Number 5 / May 1970 / Pages 456-464

Paper / Analysis / dx.doi.org/10.13182/NT70-A28691

Radioisotope Neutron Activation Analyzer for Process Control Analysis

Juhani Kuusi

Nuclear Technology / Volume 8 / Number 5 / May 1970 / Pages 465-473

Paper / Analysis / dx.doi.org/10.13182/NT70-A28692

Number 6

Table of Contents
Solubility of Metal Corrosion Products(C. Rogers McCullough)
Corrigendum
Properties of Refractory Metals(Charles H. Pitt)
The Careless Atom(John O. Mingle)
Methods in Subnuclear Physics, Vol. III (Proceedings of the International School of Elementary Particle Physics, Herceg-Novi)(Thomas H. Fields)

Increasing Maximum Enrichment Processing Capability Through Criticality Calculations

D. L. Dunaway, G. P. Miller, W. A. Johnson

Nuclear Technology / Volume 8 / Number 6 / June 1970 / Pages 482-487

Fuel Cycle / dx.doi.org/10.13182/NT70-A28647

Gas Pulse Impregnation of Graphite with Carbon

R. L. Beatty, D. V. Kiplinger

Nuclear Technology / Volume 8 / Number 6 / June 1970 / Pages 488-495

Fuel / dx.doi.org/10.13182/NT70-A28648

Plutonium Recycling in Heavy-Water-Moderated Thorium Reactor Systems

J. Darvas, U. Hansen, E. Teuchert

Nuclear Technology / Volume 8 / Number 6 / June 1970 / Pages 496-506

Fuel / dx.doi.org/10.13182/NT70-A28649

Compatibility of (U,Th)O₂ with Graphite During Irradiation

J. A. Conlin, D. R. Cuneo, E. L. Long, Jr., C. L. Segasser

Nuclear Technology / Volume 8 / Number 6 / June 1970 / Pages 507-515

Material / dx.doi.org/10.13182/NT70-A28650

The Rapid Acquisition and Analysis of Gamma-Spectrometer Data Using a Small Computer

N. I.Sax, J. C. Daly

Nuclear Technology / Volume 8 / Number 6 / June 1970 / Pages 516-521

Instrument / dx.doi.org/10.13182/NT70-A28651

Use of a Pulse Detector for Reactor Noise Measurements

J. R. Trinko, Jr., S. H. Hanauer

Nuclear Technology / Volume 8 / Number 6 / June 1970 / Pages 522-530

Technique / dx.doi.org/10.13182/NT70-A28652

Neutron Source-Strength Determination by Student Laboratories

B. W. McGhee, W. W. Graham, III, M. R. Haroon

Nuclear Technology / Volume 8 / Number 6 / June 1970 / Pages 531-535

Education / dx.doi.org/10.13182/NT70-A28653

Fabrication of a ²³⁸Pu Heat Source for a Cardiac Pacemaker

D. L. Fleming, C. O. Brewer, D. L. Coffey

Nuclear Technology / Volume 8 / Number 6 / June 1970 / Pages 536-538

Radioisotope / dx.doi.org/10.13182/NT70-A28654