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Volume 17

Number 1

A Theory for Predicting Pressure Gradients for Two-Phase Critical Flow

Hans K. Fauske

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 1-7

Technical Paper / dx.doi.org/10.13182/NSE63-A17204

Orthogonal Polynomial Angular Expansion of the Boltzmann Equation

G. C. Pomraning, M. Clark, Jr.

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 8-17

Technical Paper / dx.doi.org/10.13182/NSE63-A17205

Simulated Boiling Water Reactor and Superheat Reactor Corrosion Facility

M. D. Fitzsimmons, W. L. Pearl, M. Siegler

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 18-29

Technical Paper / dx.doi.org/10.13182/NSE63-A17206

Fuel Cladding Corrosion Testing in Simulated Superheat Reactor Environment Phase I. General Corrosion Type 304 Stainless Steel

G. G. Gaul, W. L. Pearl

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 30-41

Technical Paper / dx.doi.org/10.13182/NSE63-A17207

Resonance Absorption and the Resonance Disadvantage Factor

S. Iijima

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 42-46

Technical Paper / dx.doi.org/10.13182/NSE63-A17208

Initial Conversion Ratios and Fast Fission Factors in Heavy-Water Natural-Uranium Lattices Using 19-Element UO2 Fuel Rods

B. G. Chidley, T. J. Manuel, P. R. Tunnicliffe

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 47-54

Technical Paper / dx.doi.org/10.13182/NSE63-A17209

Transport Solutions to the One-Dimensional Critical Problem

George J. Mitsis

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 55-64

Technical Paper / dx.doi.org/10.13182/NSE63-A17210

Synthetic Method Solution of the Transport Equation

H. J. Kopp

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 65-74

Technical Paper / dx.doi.org/10.13182/NSE63-1

Research Facility for the Synthesis and Fabrication of Refractory Plutonium Materials

F. A. Saulino, J. C. Andersen, K. M. Taylor

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 75-81

Technical Paper / dx.doi.org/10.13182/NSE63-A17212

The Investigation of Nonelastic Cross Sections for Iron by the Nanosecond Pulsed Neutron Source Technique

L. E. Beghian, A. E. Profio, J. Weber, S. Wilensky

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 82-90

Technical Paper / dx.doi.org/10.13182/NSE63-A17213

Propagation of Neutron Waves in Moderating Media

R. B. Perez, R. E. Uhrig

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 90-100

Technical Paper / dx.doi.org/10.13182/NSE63-A17214

A General Method for Evaluating the Effects of Uncertainties in Design Variables on Core Thermal Performance

A. C. Nelson, JR., W. S. Minkler

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 101-110

Technical Paper / dx.doi.org/10.13182/NSE63-A17215

Symmetry Properties of Some Eigenfunctions Occurring in Reactor Analysis

Mark Goldsmith

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 111-124

Technical Paper / dx.doi.org/10.13182/NSE17-111-124

Gamma-Ray Scattering by Concrete Surfaces

Eric T. Clarke, John F. Batter

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 125-130

Technical Paper / dx.doi.org/10.13182/NSE63-A17217

Neutron Rethermalization in Graphite and Water

R. A. Bennett

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 131-143

Technical Paper / dx.doi.org/10.13182/NSE63-A17218

Effective Resonance Integral for Pu240 in Plutonium-Aluminum Alloy Rods

P. F. Nichols

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 144-148

Technical Paper / dx.doi.org/10.13182/NSE63-A17219

Mechanical Dejacketing of Liquid-Metal-Bonded Nuclear Fuels: An Evaluation of a Hydraulic Method and Two Alternative Methods with Spent Fuel from Core 1 of the Sodium Reactor Experiment

C. D. Watson, G. A. West, W. F. Schaffer, JR.

Nuclear Science and Engineering / Volume 17 / Number 1 / September 1963 / Pages 149-164

Technical Paper / dx.doi.org/10.13182/NSE63-A17220