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Volume 15

Number 2

  • Table of Contents
  • Authors(Loren C. Schmid, V. O. Uotinen, W. P. Stinson, S. P. Singh, J. K. Bahl, M. D. Freshley, Max D. Freshley, M. D. Freshley, L. J. Harrison, Darrell F. Newman, M. D. Freshley, P. E. Coudron, R. P. Matsen, L. C. Schmid, M. D. Freshley, E. A. Aitken, D. C. Wadekamper, R. L. Johnson, W. G. Lussie, L. G. Faust, L. W. Brackenbush, R. C. Smith, L. L. Nichols, D. W. Brite, V. O. Uotinen, J. H. Lauby, L. C. Schmid, W. P. Stinson, R. C. Liikala, V. O. Uotinen, U. P. Jenquin, L. C. Schmid, D. E. Christensen, B. H. Duane, R. C. Liikala, R. P. Matsen)
  • Preface: Plutonium Utilization in Commercial Power Reactors(Loren C. Schmid)
  • Lectures in Scattering Theory(Richard K. Osborn)
  • Principles of Activation Analysis(Ralph T. Overman)

Kinetic Parameters in a Plutonium Lattice Containing Water Regions

V. O. Uotinen, W. P. Stinson, S. P. Singh

Nuclear Technology / Volume 15 / Number 2 / August 1972 / Pages 109-113

Technical Paper / Plutonium Utilization in Commercial Power Reactors / Reactor / dx.doi.org/10.13182/NT72-A31141

Plutonium and Fission Product Redistribution in Mixed-Oxide Fuels During Irradiation

J. K. Bahl, M. D. Freshley

Nuclear Technology / Volume 15 / Number 2 / August 1972 / Pages 114-124

Technical Paper / Plutonium Utilization in Commercial Power Reactors / Reactor / dx.doi.org/10.13182/NT72-A31142

Mixed-Oxide Fuel Irradiations in the Plutonium Recycle Test Reactor

M. D. Freshley

Nuclear Technology / Volume 15 / Number 2 / August 1972 / Pages 125-176

Technical Paper / Plutonium Utilization in Commercial Power Reactors / Reactor / dx.doi.org/10.13182/NT72-A31143

The Transient Behavior of Vipac and Pellet Thermal Reactor Oxide Fuels

M. D. Freshley, L. J. Harrison

Nuclear Technology / Volume 15 / Number 2 / August 1972 / Pages 177-191

Technical Paper / Plutonium Utilization in Commercial Power Reactors / Reactor / dx.doi.org/10.13182/NT72-A31144

Measurement of k and Relative Reaction Rates in an H2O-Moderated UO2-PuO2 Particulate Fueled Lattice

Darrell F. Newman

Nuclear Technology / Volume 15 / Number 2 / August 1972 / Pages 192-208

Technical Paper / Plutonium Utilization in Commercial Power Reactors / Reactor / dx.doi.org/10.13182/NT72-A31145

The Defect Performance of UO2-PuO2 Thermal Reactor Fuel

M. D. Freshley

Nuclear Technology / Volume 15 / Number 2 / August 1972 / Pages 209-228

Technical Paper / Plutonium Utilization in Commercial Power Reactors / Reactor / dx.doi.org/10.13182/NT72-A31146

The Determination of Ratios of Effective Cross Sections from Burnup Data from the Saxton Plutonium Program

P. E. Coudron, R. P. Matsen, L. C. Schmid

Nuclear Technology / Volume 15 / Number 2 / August 1972 / Pages 229-238

Technical Paper / Plutonium Utilization in Commercial Power Reactors / Reactor / dx.doi.org/10.13182/NT72-A31147

Behavior of Discrete Plutonium-Dioxide Particles in Mixed-Oxide Fuel During Rapid Power Transients

M. D. Freshley, E. A. Aitken, D. C. Wadekamper, R. L. Johnson, W. G. Lussie

Nuclear Technology / Volume 15 / Number 2 / August 1972 / Pages 239-248

Technical Paper / Plutonium Utilization in Commercial Power Reactors / Reactor / dx.doi.org/10.13182/NT72-A31148

Radiation Dose Rates from UO2-PuO2 Thermal Reactor Fuels

L. G. Faust, L. W. Brackenbush, R. C. Smith, L. L. Nichols, D. W. Brite

Nuclear Technology / Volume 15 / Number 2 / August 1972 / Pages 249-256

Technical Paper / Plutonium Utilization in Commercial Power Reactors / Reactor / dx.doi.org/10.13182/NT72-A31149

Lattices of Plutonium-Enriched Rods in Light Water—Part I: Experimental Results

V. O. Uotinen, J. H. Lauby, L. C. Schmid, W. P. Stinson

Nuclear Technology / Volume 15 / Number 2 / August 1972 / Pages 257-271

Technical Paper / Plutonium Utilization in Commercial Power Reactors / Reactor / dx.doi.org/10.13182/NT72-A31150

Lattices of Plutonium-Enriched Rods in Light Water—Part II: Theoretical Analysis of Plutonium-Fueled Systems

R. C. Liikala, V. O. Uotinen, U. P. Jenquin

Nuclear Technology / Volume 15 / Number 2 / August 1972 / Pages 272-296

Technical Paper / Plutonium Utilization in Commercial Power Reactors / Reactor / dx.doi.org/10.13182/NT72-A31151

Spectrum-Averaged Cross Sections Deduced from Burnup Data and Their Application to Methods Verification

L. C. Schmid, D. E. Christensen, B. H. Duane, R. C. Liikala, R. P. Matsen

Nuclear Technology / Volume 15 / Number 2 / August 1972 / Pages 297-318

Technical Paper / Plutonium Utilization in Commercial Power Reactors / Reactor / dx.doi.org/10.13182/NT72-A31152