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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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NSE80-A20125