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Volume 39

Number 1

A Generalization of the Finite Difference Approximation Method with an Application to Space-Time Nuclear Reactor Kinetics

Raymond E. Alcouffe, Robert W. Albrecht

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 1-13

Technical Paper / dx.doi.org/10.13182/NSE70-A21166

Improvements in Fast Reactor Space-Energy Synthesis

R. J. Neuhold, K. O. Ott

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 14-24

Technical Paper / dx.doi.org/10.13182/NSE70-A21167

Doppler Broadening in a Medium with Both Temperature and Boundary Motion

S. T. Perkins

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 25-31

Technical Paper / dx.doi.org/10.13182/NSE70-A21168

Doppler Effect Studies Using Multilevel Formalism

R. N. Hwang

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 32-49

Technical Paper / dx.doi.org/10.13182/NSE70-A21169

Determination of Fission Density in 235U and Implications from Its Mass Distribution

Petru Popa, Marcel De Coster, Pieter H. M. Van Assche

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 50-55

Technical Paper / dx.doi.org/10.13182/NSE70-A21170

The Influence of a Reentrant Hole on Measurements of Fast and Thermal Neutron Spectra

Frank McGirt, Martin Becker

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 56-66

Technical Paper / dx.doi.org/10.13182/NSE70-A21171

Fast Neutron Cross Sections of Hafnium, Gadolinium, and Samarium

G. L. Sherwood, A. B. Smith, J. F. Whalen

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 67-80

Technical Paper / dx.doi.org/10.13182/NSE70-A21172

Gamma-Ray Spectra of the Products of Thermal-Neutron Fission of 235U at Selected Times after Fission

L. R. Bunney, D. Sam

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 81-91

Technical Paper / dx.doi.org/10.13182/NSE70-A21173

Theoretical Dose Transmission and Reflection Probabilities for 0.2-10.0 MeV Photons Obliquely Incident on Finite Concrete Barriers

W. O. Doggett, Fred A. Bryan, Jr.

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 92-104

Technical Paper / dx.doi.org/10.13182/NSE70-1

Construction of Lyapunov Functions for Nonlinear Reactor Stability Studies

M. A. Pai, V. R. Sastry, M. Ananda Mohan

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 105-107

Technical Note / dx.doi.org/10.13182/NSE70-A21175

Comparison of Methods for Determining Moderator Level Reactivity Coefficients

S. E. Wennemo-Hanssen

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 107-109

Technical Note / dx.doi.org/10.13182/NSE70-A21176

Control Rod Programming Optimization Using Dynamic Programming

William B. Terney, Henri Fenech

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 109-114

Technical Note / dx.doi.org/10.13182/NSE70-A21177

A Theory of Control-Rod Programming Optimization in Two-Region Reactors

Hiroshi Motoda, Toshio Kawai

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 114-118

Technical Note / dx.doi.org/10.13182/NSE70-A21178

Surface Multiplication

R. E. Wilson, R. J. Hall, E. D. Clayton

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 119-120

Technical Note / dx.doi.org/10.13182/NSE70-A21179

The Influence of the Density Effect on Electron-Induced Cascade Showers in Water and Aluminum

Harold L. Beck

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 120-121

Technical Note / dx.doi.org/10.13182/NSE70-A21180

Effective Equally Limiting Hot Channels in Reactor Thermal Design

A. Amendola

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 121-123

Technical Note / dx.doi.org/10.13182/NSE70-A21181

The Effect of Stored Energy on Measurements of Thermal Diffusivity During Irradiation

R. M. Carroll, R. B. Perez, O. Sisman

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 123-126

Technical Note / dx.doi.org/10.13182/NSE70-A21182

Radiation Heat Transfer in Ceramic Oxide Fuel Elements

J. A. Stoddard, N. J. McCormick

Nuclear Science and Engineering / Volume 39 / Number 1 / January 1970 / Pages 126-129

Technical Note / dx.doi.org/10.13182/NSE70-A21183