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Volume 23

Number 2

Mass-Fission-Yield Curve for Americium-241

R. R. Rickard, C. F. Goeking, E. I. Wyatt

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 115-118

Technical Paper / dx.doi.org/10.13182/NSE65-A28135

Dynamic Analysis of Coolant Circulation in Boiling-Water Nuclear Reactors — Part I

C. K. Sanathanan, J. C. Carter, F. Miraldi

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 119-129

Technical Paper / dx.doi.org/10.13182/NSE65-A28136

Dynamic Analysis of Coolant Circulation in Boiling-Water Nuclear Reactors — Part II

C. K. Sanathanan, J. C. Carter, F. Miraldi

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 130-137

Technical Paper / dx.doi.org/10.13182/NSE65-A28137

Differential Dose-Rate Measurements of Backscattered Gamma Rays from Concrete, Aluminum and Steel

L. G. Haggmark, T. H. Jones, N. E. Scofield, W. J. Gurney

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 138-149

Technical Paper / dx.doi.org/10.13182/NSE65-A28138

Criticality of Homogeneous Plutonium Oxide-Plastic Compacts at H:Pu=15

C. R. Richey, J. D. White, E. D. Clayton, R. C. Lloyd

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 150-158

Technical Paper / dx.doi.org/10.13182/NSE65-A28139

The Decay of Equilibrium Neutron Flux Inside Beryllium Blocks at Different Temperatures

I. C. Goyal, L. S. Kothari

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 159-166

Technical Paper / dx.doi.org/10.13182/NSE65-A28140

Equilibrium Spectra and Diffusion Lengths of Neutrons in Semi-Infinite Moderator Block: Part II: Effect of ‘Trapped’ and Cold Neutrons

P. S. Grover, L. S. Kothari

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 167-169

Technical Paper / dx.doi.org/10.13182/NSE65-A28141

New Approximate Solution of Space- and Energy-Dependent Reactor Kinetics

Tsutomu Hoshino, Jiro Wakabayashi, Shigenori Hayashi

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 170-182

Technical Paper / dx.doi.org/10.13182/NSE65-A28142

A Simplified Nonlinear Model for Qualitative Study of Reactor Power-Distribution Transients

H. Hurwitz, Jr.

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 183-187

Technical Paper / dx.doi.org/10.13182/NSE65-A28143

Nuclear-Fuel-Depletion Measuring Device

L. B. Freeman

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 188-189

Technical Note / dx.doi.org/10.13182/NSE65-A28144

Fission-Product Effects in Molten Chloride Fast-Reactor Fuels

M. G. Chasanov

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 189-190

Technical Note / dx.doi.org/10.13182/NSE65-A28145

Neutron Diffusion Theory

J. D. Stewart

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 190-192

Technical Note / dx.doi.org/10.13182/NSE65-A28146

The Energy-Dependent Total Neutron Cross Section of Polyethylene

S. B. Armstrong

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 192-194

Technical Note / dx.doi.org/10.13182/NSE65-A28147

Inelastic Scattering of Slow Neutrons by Zirconium and Titanium Hydrides

S. S. Pan, F. J. Webb

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 194-197

Technical Note / dx.doi.org/10.13182/NSE65-A28148

Some Remarks on the Reduction of Thermal-Neutron Activation Rates to a Differential Spectrum

H. Ibarra, R. Sher

Nuclear Science and Engineering / Volume 23 / Number 2 / October 1965 / Pages 197-199

Technical Note / dx.doi.org/10.13182/NSE65-A28149