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Volume 14

Number 3

Table of Contents
Authors(Robert W. Albrecht, David A. Greene, H. L. Beck, J. A. DeCampo, C. V. Gogolak, W. M. Lowder, J. E. McLaughlin, P. D. Raft, M. N, Özişik, M. D. Silverman, V. F. Baston, J. H. McFadden, W. A. Yuill, W. J. Lackey, R. A. Bradley, T. R. Herold, Dennis G. Vasilik, Richard L. Murri, George P. Fisher, Dong H. Nguyen, Robert G. Bennett, J. F. Bates, J. L. Straalsund)
A Practical Approach to Nuclear Criticality Safety II—Critique of a Model(William Bradley Lewis)
Irradiation Effects on Structural Alloys for Nuclear Reactor Applications(John O. Schiffgens)
A N-34 Experiments in Nuclear Science(Wallace H. Fuller)
Nuclear Data for Reactors(David Okrent)
Earthquake Engineering for Nuclear Reactor Facilities(Craig Smith)

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

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