Volume 74

Number 1 | Number 2 | Number 3

Number 1

Table of Contents
On the Factorized Kernel Approach for Solving Multidimensional Neutron Transport Problems(D. C. Sahni)
Reply to “On the Factorized Kernel Approach for Solving Multidimensional Neutron Transport Problems”(F. Premuda)
Nuclear Energy in Germany(James A. Lane)

A Transport Theoretic P_N Approximation

K. Ganguly, A. Sengupta

Nuclear Science and Engineering / Volume 74 / Number 1 / April 1980 / Pages 1-12

Technical Paper / dx.doi.org/10.13182/NSE80-A18940

Application of the Multigroup Collision Probability Method to Selengut's Theory of Overlapping Neutron Spectra

G. Kamelander, F. Putz

Nuclear Science and Engineering / Volume 74 / Number 1 / April 1980 / Pages 13-22

Technical Paper / dx.doi.org/10.13182/NSE80-A18941

Neutron Wave Propagation in Heavy Water

Ashok Sadhwani, Ashok Kumar, L. S. Kothari

Nuclear Science and Engineering / Volume 74 / Number 1 / April 1980 / Pages 23-28

Technical Paper / dx.doi.org/10.13182/NSE80-A18942

Measurement of the ²³⁵U(n, 2n) Cross Section Between Threshold and 13 MeV

J. Frehaut, A. Bertin, R. Bois

Nuclear Science and Engineering / Volume 74 / Number 1 / April 1980 / Pages 29-33

Technical Paper / dx.doi.org/10.13182/NSE80-A18943

Doppler Effect Measurements of Tin by the Filtered Neutron Beam Technique

Francis Y. Tsang, Robert M. Brugger

Nuclear Science and Engineering / Volume 74 / Number 1 / April 1980 / Pages 34-39

Technical Paper / dx.doi.org/10.13182/NSE80-A18944

A Nonequilibrium Vapor Production Model for Critical Flow

W. C. Rivard, J. R. Travis

Nuclear Science and Engineering / Volume 74 / Number 1 / April 1980 / Pages 40-48

Technical Paper / dx.doi.org/10.13182/NSE80-A18945

A Sensitivity Study on the Influence of the Choice of the Mean Resonance Data Set in the Unresolved Resonance Region on the Doppler Effect Calculations

S. Ganesan

Nuclear Science and Engineering / Volume 74 / Number 1 / April 1980 / Pages 49-51

Technical Note / dx.doi.org/10.13182/NSE80-A18946

A Study of Variance in Energy-Dependent Monte Carlo Transport Problems

P. K. Sarkar, M. A. Prasad

Nuclear Science and Engineering / Volume 74 / Number 1 / April 1980 / Pages 52-60

Technical Note / dx.doi.org/10.13182/NSE80-A18947

On the Homogenization of Uniform Lattices

T. Duracz

Nuclear Science and Engineering / Volume 74 / Number 1 / April 1980 / Pages 61-64

Technical Note / dx.doi.org/10.13182/NSE80-A18948

Number 2

Table of Contents
Eigenvalues of the Neutron Transport Equation with Anisotropic Scattering(N. G. Sjöstrand)
Reply to a Comment on “Eigenvalues of the Neutron Transport Equation with Anisotropic Scattering”(Trine-Yie Dawn)
Nuclear Power Plant Engineering(Ronald J. Onega)
On the Correct Use of the Bayesian Method for Reactor Core Melt Frequency(Harry F. Martz, Jr.)

Characteristics and Stability Analyses for Two-Phase Flow Equation Systems with Viscous Terms

Masahiko Arai

Nuclear Science and Engineering / Volume 74 / Number 2 / May 1980 / Pages 77-83

Technical Paper / dx.doi.org/10.13182/NSE80-A19624

A Symbiotic Water Breeder Reactor System

Yigal Ronen, Samuel Carmona

Nuclear Science and Engineering / Volume 74 / Number 2 / May 1980 / Pages 84-94

Technical Paper / dx.doi.org/10.13182/NSE80-A19625

Measurements of Moderator Temperature Coefficients of Reactivity for Pressure-Tube-Type Reactors

T. Otsuka, N. Fukumura, Y. Hachiya

Nuclear Science and Engineering / Volume 74 / Number 2 / May 1980 / Pages 95-105

Technical Paper / dx.doi.org/10.13182/NSE80-A19626

Fission-Product Energy Release for Times Following Thermal-Neutron Fission of ²³⁵U Between 2 and 14 000 s

J. K. Dickens, T. A. Love, J. W. McConnell, R. W. Peelle

Nuclear Science and Engineering / Volume 74 / Number 2 / May 1980 / Pages 106-129

Technical Paper / dx.doi.org/10.13182/NSE80-A19627

A Separation Method for the Transport Equation and Sensitivity Theory for Fusion-Fission Hybrid Analysis

M. Z. Youssef, R. W. Conn

Nuclear Science and Engineering / Volume 74 / Number 2 / May 1980 / Pages 130-139

Technical Paper / dx.doi.org/10.13182/NSE80-A19628

Temperature Effects on Charged-Particle-Induced Cross Sections

Dermott E. Cullen, Robert J. Howerton, Ernest F. Plechaty

Nuclear Science and Engineering / Volume 74 / Number 2 / May 1980 / Pages 140-147

Technical Note / dx.doi.org/10.13182/NSE80-A19629

Application of Generalized Variational Principles to Controlled Thermonuclear Reactor Neutronics Analysis

E. T. Cheng

Nuclear Science and Engineering / Volume 74 / Number 2 / May 1980 / Pages 147-153

Technical Note / dx.doi.org/10.13182/NSE80-A19630

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