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Volume 11

Number 1

  • Table of Contents
  • Authors(J. G. Guppy, R. L. Brehm, Pekka Jauho, Risto Tarjanne, C. R. Schmitt, C. M. Walter, P. G. Shewmon, J. P. Bacca, H. E. McCoy, R. E. Gehlbach, P. C. Curtayne, A. R. Boulogne, J. P. Faraci, John N. Hamawi, Harry J. Reilly, Lawrence E. Peters, Jr., W. R. Sheets, Werner Brandt, Michael D. D’Agostino, Anthony J. Favale, R. M. Rubin, R. E. Faw, D. L. Smith, K. M. Barry, J. A. Corbett, Peter G. Salgado, Fred P. Schilling, Gerald T. Brock, Kermit L. Holman, A. A. Harms, S. I. Schreiner)
  • MHD Power Generation: Engineering Aspect(Fritz W. Mezger)
  • Survey of an Emerging Service Industry: Technology Transfer(Joseph G. Gratton)

Modeling of Thermionic Reactor Systems for Dynamics Studies

J. G. Guppy, R. L. Brehm

Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 7-18

Technical Paper / Reactor / dx.doi.org/10.13182/NT71-A30897

Pulsed-Neutron and Exponential Experiments with Mixed-Fuel Lattices

Pekka Jauho, Risto Tarjanne

Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 19-28

Technical Paper / Reactor / dx.doi.org/10.13182/NT71-A30898

A Vibrating Bar Technique for Preparing Carbon Microspheres

C. R. Schmitt

Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 29-37

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT71-A30899

Application of Fuel-Element Modeling Codes to EBR-II Driver Fuel

C. M. Walter, P. G. Shewmon, J. P. Bacca

Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 38-44

Technical Paper / Fuel / dx.doi.org/10.13182/NT71-A30900

Influence of Irradiation Temperature on the Creep-Rupture Properties of Hastelloy-N

H. E. McCoy, R. E. Gehlbach

Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 45-60

Technical Paper / Material / dx.doi.org/10.13182/NT71-A30901

Techniques in Monte Carlo Analysis Applied to the Nuclear Density Gauge

P. C. Curtayne

Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 61-74

Technical Paper / Radioisotope / dx.doi.org/10.13182/NT71-A30902

Californium-252 Neutron Sources for Industrial Applications

A. R. Boulogne, J. P. Faraci

Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 75-83

Technical Paper / Radioisotope / dx.doi.org/10.13182/NT71-A30903

A Useful Recurrence Formula for the Equations of Radioactive Decay

John N. Hamawi

Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 84-88

Technical Paper / Radioisotope / dx.doi.org/10.13182/NT71-A30904

Calorimetric Determination of Relative Gamma Heating in Materials of Various Thicknesses and Atomic Numbers

Harry J. Reilly, Lawrence E. Peters, Jr.

Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 89-95

Technical Paper / Shielding / dx.doi.org/10.13182/NT71-A30905

Reciprocal Multiplication Meter

W. R. Sheets

Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 96-98

Technical Paper / Instrument / dx.doi.org/10.13182/NT71-A30906

Alpha-Particle Densitometer with Variable Response

Werner Brandt, Michael D. D’Agostino, Anthony J. Favale

Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 99-104

Technical Paper / Instrument / dx.doi.org/10.13182/NT71-A30907

Exposure Angular Distributions in Air Above Disk Isotropic Cobalt-60 Sources

R. M. Rubin, R. E. Faw

Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 105-114

Technical Paper / Radiation / dx.doi.org/10.13182/NT71-A30908

An Equilibration Method for Measuring Low-Oxygen Activities in Liquid Sodium

D. L. Smith

Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 115-119

Technical Paper / Analysis / dx.doi.org/10.13182/NT71-A30909

Measurement of Neutron Fluence by Neptunium-237 and Uranium-238 Fission Dosimeters

K. M. Barry, J. A. Corbett

Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 120-130

Technical Paper / Analysis / dx.doi.org/10.13182/NT71-A30910

Determination of Pyrocarbon Thermal Conductivity by the Burst-Reactor Technique

Peter G. Salgado, Fred P. Schilling, Gerald T. Brock, Kermit L. Holman

Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 131-143

Technical Paper / Technique / dx.doi.org/10.13182/NT71-A30911

An Expository Derivation of Neutron Transport Equations

A. A. Harms, S. I. Schreiner

Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 144-149

Technical Paper / Education / dx.doi.org/10.13182/NT71-A30912