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Home / Publications / Journals / Nuclear Science and Engineering / Volume 74 / Number 3

Volume 74

Number 3

Table of Contents
Radiation Detection and Measurement(Louis Costrell)
Laminar, Transition, and Turbulent Parallel Flow Pressure Drop Across Wire-Wrap-Spaced Rod Bundles(F. C. Engel, R. A. Markley, A. A. Bishop)

An Analytical Angular Integration Technique for Generating Multigroup Transfer Matrices

J. A. Bucholz

Nuclear Science and Engineering / Volume 74 / Number 3 / June 1980 / Pages 163-167

Technical Paper / dx.doi.org/10.13182/NSE80-A20115

Finite Element Basis in Data Adjustment

F. Schmittroth, R. E. Schenter

Nuclear Science and Engineering / Volume 74 / Number 3 / June 1980 / Pages 168-177

Technical Paper / dx.doi.org/10.13182/NSE80-A20116

A Multigroup Formalism to Solve the Fokker-Planck Equation Characterizing Charged Particle Transport

P. -A. Haldy, J. Ligou

Nuclear Science and Engineering / Volume 74 / Number 3 / June 1980 / Pages 178-184

Technical Paper / dx.doi.org/10.13182/NSE80-A20117

Perturbation Theory for Inertial Confinement Pellet Fusion Problems

E. Greenspan

Nuclear Science and Engineering / Volume 74 / Number 3 / June 1980 / Pages 185-192

Technical Paper / dx.doi.org/10.13182/NSE80-A20118

Nuclear Fuel Trajectories of Fusion-Fission Symbionts

J. K. Presley, A. A. Harms, M. Heindler

Nuclear Science and Engineering / Volume 74 / Number 3 / June 1980 / Pages 193-198

Technical Paper / dx.doi.org/10.13182/NSE80-A20119

A Methodology for Calculating the Expected Number of Failures of a System Undergoing a Phased Mission

D. F. Montague, J. B. Fussell

Nuclear Science and Engineering / Volume 74 / Number 3 / June 1980 / Pages 199-209

Technical Paper / dx.doi.org/10.13182/NSE80-A20120

Discrete Ordinates Calculations of the Importance Factor of a Neutron Source

M. Caro, J. Ligou

Nuclear Science and Engineering / Volume 74 / Number 3 / June 1980 / Pages 210-213

Technical Note / dx.doi.org/10.13182/NSE80-A20121

Reduction of Computational Time for Point Detector Estimator in Monte Carlo Transport Code

Hiromasa Iida, Yasushi Seki

Nuclear Science and Engineering / Volume 74 / Number 3 / June 1980 / Pages 213-215

Technical Note / dx.doi.org/10.13182/NSE80-A20122

Interrelating Differential and Integral Nuclear Data

S. Pearlstein

Nuclear Science and Engineering / Volume 74 / Number 3 / June 1980 / Pages 215-219

Technical Note / dx.doi.org/10.13182/NSE80-A20123

Measurement of the ⁷Li(n,n'γ)⁷Li* (0.478-MeV) Cross Section from 0.5 to 5.0 Mev

D. K. Olsen, G. L. Morgan, J. W. McConnell

Nuclear Science and Engineering / Volume 74 / Number 3 / June 1980 / Pages 219-222

Technical Note / dx.doi.org/10.13182/NSE80-A20124

Fission Fragment Backscattering Corrections to Absolute Fission Counting Rate Measurements

G. Coddens, C. Wagemans, A. J. Deruytter

Nuclear Science and Engineering / Volume 74 / Number 3 / June 1980 / Pages 223-224

Technical Note / dx.doi.org/10.13182/NSE80-A20125

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