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Volume 14

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Number 1

Physics of Nuclear Materials Safeguards Techniques

Tsahi Gozani

Nuclear Technology / Volume 14 / Number 1 / April 1972 / Pages 8-19

Technical Paper / Session on Physics of Nuclear Materials Safeguards / Reactor / dx.doi.org/10.13182/NT72-A31093

Near Barrier Fission Induced with Photons

John R. Huizenga

Nuclear Technology / Volume 14 / Number 1 / April 1972 / Pages 20-32

Technical Paper / Session on Physics of Nuclear Materials Safeguards / Reactor / dx.doi.org/10.13182/NT14-1-20

Low Energy Photofission of Heavy Elements—Experimental Results

R. L. Bramblett, T. Gozani, R. O. Ginaven, D. E. Rundquist

Nuclear Technology / Volume 14 / Number 1 / April 1972 / Pages 33-41

Technical Paper / Session on Physics of Nuclear Materials Safeguards / Reactor / dx.doi.org/10.13182/NT72-A31095

Theory of Delayed-Neutron Physics

L. Tomlinson

Nuclear Technology / Volume 14 / Number 1 / April 1972 / Pages 42-52

Technical Paper / Session on Physics of Nuclear Materials Safeguards / Reactor / dx.doi.org/10.13182/NT72-A31096

Physics of Delayed Neutrons—Recent Experimental Results

G. Robert Keepin

Nuclear Technology / Volume 14 / Number 1 / April 1972 / Pages 53-58

Technical Paper / Session on Physics of Nuclear Materials Safeguards / Reactor / dx.doi.org/10.13182/NT72-A31097

Application of Neutron Techniques in the Nondestructive Assay of Fissile Materials

D. Stegemann

Nuclear Technology / Volume 14 / Number 1 / April 1972 / Pages 59-64

Technical Paper / Session on Physics of Nuclear Materials Safeguards / Reactor / dx.doi.org/10.13182/NT72-A31098

A Model for the High Temperature Swelling of Clad Oxide Fuel

Arthur A. Bauer

Nuclear Technology / Volume 14 / Number 1 / April 1972 / Pages 65-70

Technical Paper / Session on Physics of Nuclear Materials Safeguards / Fuel / dx.doi.org/10.13182/NT72-A31099

Some Effects of Water Sprinklers on Array Criticality Safety Analyses

G. R. Handley

Nuclear Technology / Volume 14 / Number 1 / April 1972 / Pages 71-75

Technical Paper / Session on Physics of Nuclear Materials Safeguards / Fuel / dx.doi.org/10.13182/NT72-A31100

In Situ Incorporation of Nuclear Waste in Deep Molten Silicate Rock

Jerry J. Cohen, Arthur E. Lewis, Robert L. Braun

Nuclear Technology / Volume 14 / Number 1 / April 1972 / Pages 76-88

Technical Paper / Session on Physics of Nuclear Materials Safeguards / Radioactive Waste / dx.doi.org/10.13182/NT72-A31101

The Atomic Energy Research Establishment Miniature Nuclear Battery

A. W. Penn, M. H. Brown, J. Myatt, M. J. Poole

Nuclear Technology / Volume 14 / Number 1 / April 1972 / Pages 89-95

Technical Paper / Session on Physics of Nuclear Materials Safeguards / Radioisotope / dx.doi.org/10.13182/NT72-A31102

Copper Assay of Biomaterials with Neutron Activation

N. Spronk, R. J. Van Hoek

Nuclear Technology / Volume 14 / Number 1 / April 1972 / Pages 96-104

Technical Paper / Session on Physics of Nuclear Materials Safeguards / Analysis / dx.doi.org/10.13182/NT72-A31103

Precision and Source of Variation of Oxygen-to-Metal Determinations for (U, Pu)O2

W. J. Lackey, R. A. Bradley, W. H. Pechin, T. L. Hebble

Nuclear Technology / Volume 14 / Number 1 / April 1972 / Pages 105-107

Technical Paper / Session on Physics of Nuclear Materials Safeguards / Material / dx.doi.org/10.13182/NT72-A31104

Number 2

  • Table of Contents
  • Authors(P. Civita, P. Fornaciari, T. Mazzanti, Barry N. Naft, Alexander Sesonske, J. C. Carter, R. T. Purviance, J. F. Boland, C. E. Dickerman, J. E. Hanson, A. D. Vaughn, R. I. Smith, R. O. Meyer, B. J. Buescher, Morton I. Goldman, Lee A. James, Ray C. Daniel, Miles Reynolds, Jr., K. G. Porges, R. H. Augustson, C. N. Henry, C. R. Weisbin, W. L. Filippone, F. J. Munno)

Optimal Operational Strategy in Nuclear Fuel Management

P. Civita, P. Fornaciari, T. Mazzanti

Nuclear Technology / Volume 14 / Number 2 / May 1972 / Pages 116-122

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT72-A31126

Pressurized Water Reactor Optimal Fuel Management

Barry N. Naft, Alexander Sesonske

Nuclear Technology / Volume 14 / Number 2 / May 1972 / Pages 123-132

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT72-A31127

First Loss of Flow Experiment with an FTR-Type Fuel Pin in the Mark-II Loop

J. C. Carter, R. T. Purviance, J. F. Boland, C. E. Dickerman, J. E. Hanson

Nuclear Technology / Volume 14 / Number 2 / May 1972 / Pages 133-145

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT72-A31128

Fuel Rod Enrichment Determination By Gamma-Ray Spectrometry

A. D. Vaughn, R. I. Smith

Nuclear Technology / Volume 14 / Number 2 / May 1972 / Pages 146-152

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT72-A31129

A Simple Method of Calculating the Radial Temperature Distribution in a Mixed-Oxide Fuel Element

R. O. Meyer, B. J. Buescher

Nuclear Technology / Volume 14 / Number 2 / May 1972 / Pages 153-156

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT72-A31130

Radioactive Waste Management and Radiation Exposure

Morton I. Goldman

Nuclear Technology / Volume 14 / Number 2 / May 1972 / Pages 157-162

Technical Paper / Radioactive waste / dx.doi.org/10.13182/NT72-A31131

The Effect of Stress Ratio on the Elevated Temperature Fatigue-Crack Propagation of Type 304 Stainless Steel

Lee A. James

Nuclear Technology / Volume 14 / Number 2 / May 1972 / Pages 163-170

Technical Paper / Materlal / dx.doi.org/10.13182/NT72-A31132

In-Pile Dimensional Changes of Zircaloy-4 Tubing Having Low Hoop Stresses (Light Water Breeder Reactor Development Program)

Ray C. Daniel

Nuclear Technology / Volume 14 / Number 2 / May 1972 / Pages 171-186

Technical Paper / Material / dx.doi.org/10.13182/NT72-A31133

Project Rulison—Summary of Results and Analyses

Miles Reynolds, Jr.

Nuclear Technology / Volume 14 / Number 2 / May 1972 / Pages 187-193

Technical Paper / Nuclear Explosive / dx.doi.org/10.13182/NT72-A31134

Note on Detectability Enhancement of Weak Neutron Burst Signals Through Multiplication

K. G. Porges

Nuclear Technology / Volume 14 / Number 2 / May 1972 / Pages 194-196

Technical Note / Instrument / dx.doi.org/10.13182/NT72-A31135

Measurement of the Uranium-235 Content in a Spent Mtr Type Fuel Element Using the Delayed-Neutron Yield Technique

R. H. Augustson, C. N. Henry, C. R. Weisbin

Nuclear Technology / Volume 14 / Number 2 / May 1972 / Pages 197-199

Technical Note / Analysis / dx.doi.org/10.13182/NT72-A31136

Vector Analysis of Time-Dependent Gamma-Ray Spectra

W. L. Filippone, F. J. Munno

Nuclear Technology / Volume 14 / Number 2 / May 1972 / Pages 200-202

Technical Note / Analysis / dx.doi.org/10.13182/NT72-A31137

Number 3

The Use of Signal Coherence for Anomaly Detection in Nuclear Reactors

Robert W. Albrecht

Nuclear Technology / Volume 14 / Number 3 / June 1972 / Pages 208-217

Technical Paper / Reactor / dx.doi.org/10.13182/NT72-A31110

Steam Generator Vessel Pressures Resulting from a Sodium-Water Reaction—A Computer Analysis with the SWEAR Code

David A. Greene

Nuclear Technology / Volume 14 / Number 3 / June 1972 / Pages 218-231

Technical Paper / Reactor / dx.doi.org/10.13182/NT72-A31111

New Perspectives on Low Level Environmental Radiation Monitoring Around Nuclear Facilities

H. L. Beck, J. A. DeCampo, C. V. Gogolak, W. M. Lowder, J. E. McLaughlin, arid P. D. Raft

Nuclear Technology / Volume 14 / Number 3 / June 1972 / Pages 232-239

Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT72-A31112

The Effects of Transverse Flow Through Graphite on Fission Product Movement in HTGR-Type Systems

M. N. Özişik, M. D. Silverman

Nuclear Technology / Volume 14 / Number 3 / June 1972 / Pages 240-246

Technical Paper / Fuel / dx.doi.org/10.13182/NT72-A31113

An Analytical Method for Calculating Steady-State Fission Gas Release

V. F. Baston, J. H. McFadden, W. A. Yuill

Nuclear Technology / Volume 14 / Number 3 / June 1972 / Pages 247-256

Technical Paper / Fuel / dx.doi.org/10.13182/NT72-A31114

Microstructure of Sol-Gel-Derived (U, Pu)O2 Microspheres and Pellets

W. J. Lackey, R. A. Bradley

Nuclear Technology / Volume 14 / Number 3 / June 1972 / Pages 257-268

Technical Paper / Fuel / dx.doi.org/10.13182/NT72-A31115

Electronic Assay of Californium-252 Neutron Sources

T. R. Herold

Nuclear Technology / Volume 14 / Number 3 / June 1972 / Pages 269-278

Technical Paper / Radioisotope / dx.doi.org/10.13182/NT72-A31116

Thermal-Neutron Radiography with a Sealed-Tube Neutron Generator and Water Moderator

Dennis G. Vasilik, Richard L. Murri, George P. Fisher

Nuclear Technology / Volume 14 / Number 3 / June 1972 / Pages 279-283

Technical Paper / Instrument / dx.doi.org/10.13182/NT72-A31117

Measurement of Fast- and Thermal-Neutron Fluxes Using a Small LiI(Eu) Crystal Detector

Dong H. Nguyen, Robert G. Bennett

Nuclear Technology / Volume 14 / Number 3 / June 1972 / Pages 284-291

Technical Paper / Instrument / dx.doi.org/10.13182/NT72-A31118

An Empirical Representation of Irradiation-Induced Swelling of Solution Treated Type 304 Stainless Steel

J. F. Bates, J. L. Straalsund

Nuclear Technology / Volume 14 / Number 3 / June 1972 / Pages 292-298

Technical Note / Material / dx.doi.org/10.13182/NT72-A31119