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Volume 56

Number 1

Table of Contents
A Comment on Anisotropic Neutron Diffusion in Lattices of the Zero-Power Plutonium Reactor Experiments(P. Köhler)
Power Plants with Air-Cooled Condensing Systems(Paul Leung)

Rate of Liquid Entrainment at the Gas-Liquid Interface of a Liquid Submerged Sonic Gas Jet

T. C. Chawla

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 1-6

Technical Paper / dx.doi.org/10.13182/NSE75-A26616

A Computational Technique to Assess Procedures for Failed-Fuel Identification

N. J. McCormick

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 7-15

Technical Paper / dx.doi.org/10.13182/NSE75-A26617

Joint Probability Distribution of Neutron Counts in Reactor Noise Analysis

M. Marseguerra

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 16-26

Technical Paper / dx.doi.org/10.13182/NSE75-A26618

Total Neutron Cross Section of Carbon from 1 keV to 15 MeV

H. T. Heaton, II, J. L. Menke, R. A. Schrack, R. B. Schwartz

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 27-36

Technical Paper / dx.doi.org/10.13182/NSE75-A26619

Delayed-Neutron Data for Reactor-Physics Analysis

R. J. Tuttle

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 37-71

Technical Paper / dx.doi.org/10.13182/NSE75-A26620

A Theory of Resonance-Group Self-Shielding

M. Segev

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 72-82

Technical Paper / dx.doi.org/10.13182/NSE75-A26621

Thermonuclear Microfission

F. Winterberg

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 83-84

Technical Note / dx.doi.org/10.13182/NSE75-A26622

Compact Tables of Functions for Use in Shielding Calculations

K. Shure, O. J. Wallace

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 84-94

Technical Note / dx.doi.org/10.13182/NSE75-A26623

A New Measurement of the ¹⁰B(n, α)⁷Li Branching Ratio

G. P. Lamaze, A. D. Carlson, M. M. Meier

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 94-96

Technical Note / dx.doi.org/10.13182/NSE75-A26624

Calculated Nickel-58 Reaction Cross Sections Around 14-MeV Neutron Energy

B. S. Wadhwa, R. K. Mohindra

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 96-98

Technical Note / dx.doi.org/10.13182/NSE75-A26625

Measured Thermal-Neutron Cross Section for the ⁵⁹Ni(n, α)⁵⁶Fe Reaction

R. D. Werner, D. C. Santry

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 98-100

Technical Note / dx.doi.org/10.13182/NSE75-A26626

A Generalized Source-Multiplication Method for Determining Reactivity

Ehud Greenspan

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 100-103

Technical Note / dx.doi.org/10.13182/NSE75-A26627

A Source-Multiplication Reactivity

Ehud Greenspan

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 103-106

Technical Note / dx.doi.org/10.13182/NSE75-A26628

An Improved Series Representation of Doppler-Broadened Resonance Absorption

Arthur Ginsberg, Martin Becker

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 106-107

Technical Note / dx.doi.org/10.13182/NSE75-A26629

A Generalized Perturbation Theory and Variational Principle for Multiple Ratios of Linear and Bilinear Functionals

Ehud Greenspan

Nuclear Science and Engineering / Volume 56 / Number 1 / January 1975 / Pages 107-112

Technical Note / dx.doi.org/10.13182/NSE75-A26630