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Number 1
Number 2

Number 3
Number 4

Number 1

Table of Contents
Comments on “Analysis of the Microfission Reactor Concept” (F. Winterberg)
Reply to “Comments on ‘Analysis of the Microfission Reactor Concept’” (R. K. Cole, Jr., J. H. Renken)
From Scientific Search to Atomic Industry (Karl Cohen)
Nuclear-Reactor Analysis (G. C. Pomraning)

Analysis of Pressure Pulse Generation Due to Gas Release from Failed Fuel Pins in a Liquid-Metal Fast Breeder Reactor
Mujid S. Kazimi
Nuclear Science and Engineering | Volume 59 | Number 1 | January 1976 | Pages 1-11
Technical Paper | doi.org/10.13182/NSE76-A26803
Neutron Capture Cross Section of Niobium-93 from 2.6 to 700 keV
R. L. Macklin
Nuclear Science and Engineering | Volume 59 | Number 1 | January 1976 | Pages 12-20
Technical Paper | doi.org/10.13182/NSE76-A26804
Criticality Safety Data Applicable to Processing Liquid-Metal Fast Breeder Reactor Fuel
R. C. Lloyd, E. D. Clayton
Nuclear Science and Engineering | Volume 59 | Number 1 | January 1976 | Pages 21-26
Technical Paper | doi.org/10.13182/NSE76-A26805
Transfer Matrix Treatments for Multigroup Monte Carlo Calculations—The Elimination of Ray Effects
L. L. Carter, C. A. Forest
Nuclear Science and Engineering | Volume 59 | Number 1 | January 1976 | Pages 27-45
Technical Paper | doi.org/10.13182/NSE76-A26806
Analysis and Comparison of Plutonium-238 Nuclear Data
M. Caner, S. Yiftah
Nuclear Science and Engineering | Volume 59 | Number 1 | January 1976 | Pages 46-50
Technical Note | doi.org/10.13182/NSE76-A26807
The Slow-Neutron Fission Cross Sections of the Common Fissile Nuclides (Revised 1975)
C. B. Bigham
Nuclear Science and Engineering | Volume 59 | Number 1 | January 1976 | Pages 50-52
Technical Note | doi.org/10.13182/NSE76-A26808
The Discrete Eigenvalue Problem for Azimuthally Dependent Transport Theory
J. Kenneth Shultis, T. R. Hill
Nuclear Science and Engineering | Volume 59 | Number 1 | January 1976 | Pages 53-56
Technical Note | doi.org/10.13182/NSE76-A26809
Neutron Transport with Temperature Feedback
A. Belleni-Morante
Nuclear Science and Engineering | Volume 59 | Number 1 | January 1976 | Pages 56-58
Technical Note | doi.org/10.13182/NSE76-A26810
Multigroup Representations of Slowing-Down Kernels in H₂O
Milton C. Edlund, Richard B. Jones, P. F. Zweifel
Nuclear Science and Engineering | Volume 59 | Number 1 | January 1976 | Pages 58-60
Technical Note | doi.org/10.13182/NSE76-A26811
On the Generalized Perturbation Methods in Time-Dependent Problems
A. Gandini
Nuclear Science and Engineering | Volume 59 | Number 1 | January 1976 | Pages 60-63
Technical Note | doi.org/10.13182/NSE76-A26812
A Finite Element Synthesis Method
Shi-tien Yang, A. F. Henry
Nuclear Science and Engineering | Volume 59 | Number 1 | January 1976 | Pages 63-67
Technical Note | doi.org/10.13182/NSE76-A26813

Number 2

Table of Contents
Estimation and Optimal Feedback Control Theory Applied to a Nuclear Boiling Water Reactor (B. Frogner, L. M. Grossman)
Methods for Detailed Thermal and Hydraulic Analysis of Water-Cooled Reactors (Joel Weisman, Robert W. Bowring)

Measurement of the Neutron Capture and Fission Cross Sections of ²³⁹Pu and ²³⁵U, 0.02 eV to 200 keV, the Neutron Capture Cross Sections of ¹⁹⁷Au, 10 to 50 keV, and Neutron Fission Cross Sections of ²³³U, 5 to 200 keV
R. Gwin, E. G. Silver, R. W. Ingle, H. Weaver
Nuclear Science and Engineering | Volume 59 | Number 2 | February 1976 | Pages 79-105
Technical Paper | doi.org/10.13182/NSE76-A15682
Fast-Neutron Total and Scattering Cross Sections of Elemental Nickel
P. Guenther, A. Smith, J. Whalen
Nuclear Science and Engineering | Volume 59 | Number 2 | February 1976 | Pages 106-116
Technical Paper | doi.org/10.13182/NSE76-A15683
Uncertainty Analysis of Fission-Product Decay-Heat Summation Methods
F. Schmittroth
Nuclear Science and Engineering | Volume 59 | Number 2 | February 1976 | Pages 117-139
Technical Paper | doi.org/10.13182/NSE76-A15684
Boundary-Value Thermal-Hydraulic Analysis of a Reactor Fuel Rod Bundle
William T. Sha, Robert C. Schmitt, P. R. Huebotter
Nuclear Science and Engineering | Volume 59 | Number 2 | February 1976 | Pages 140-160
Technical Paper | doi.org/10.13182/NSE76-A15685
A Monte Carlo Code for the Evaluation of the Thermal Design of a Nuclear Reactor Core
Kazuyoshi Miki, Kotaro Inoue
Nuclear Science and Engineering | Volume 59 | Number 2 | February 1976 | Pages 161-169
Technical Paper | doi.org/10.13182/NSE76-A15686
Generalized Padé and Chebyshev Approximations for Point Kinetics
J. P. Hennart, B. Torres Barrios
Nuclear Science and Engineering | Volume 59 | Number 2 | February 1976 | Pages 170-187
Technical Note | doi.org/10.13182/NSE76-A15687
Sensitivity Theory from a Differential Viewpoint
E. M. Oblow
Nuclear Science and Engineering | Volume 59 | Number 2 | February 1976 | Pages 187-189
Technical Note | doi.org/10.13182/NSE76-A15688
Cross-Section Sensitivity of the D-T Fusion Probability and the D-T and T-T Reaction Rates
R. T. Santoro, J. Barish
Nuclear Science and Engineering | Volume 59 | Number 2 | February 1976 | Pages 189-194
Technical Note | doi.org/10.13182/NSE76-A15689
Neutron Slowing Down with Energy-Dependent Anisotropy of Scattering
D. Stefanović
Nuclear Science and Engineering | Volume 59 | Number 2 | February 1976 | Pages 194-198
Technical Note | doi.org/10.13182/NSE76-A15690

Number 3

Table of Contents
Remarks on “Neutron Transport with Temperature Feedback” (Aldo Belleni-Morante)
Techniques in Nuclear Structure Physics (T. F. Parkinson)

Monte Carlo Surface Density Solution to the Dirichlet Heat Transfer Problem
T. J. Hoffman, N. E. Banks
Nuclear Science and Engineering | Volume 59 | Number 3 | March 1976 | Pages 205-214
Technical Paper | doi.org/10.13182/NSE76-A26819
A General Method for Generating Effective Resonance Cross Sections for Heterogeneous Media
K. D. Kirby, R. A. Karam
Nuclear Science and Engineering | Volume 59 | Number 3 | March 1976 | Pages 215-230
Technical Paper | doi.org/10.13182/NSE76-A26820
The ¹⁶⁵Ho(n, γ) Standard Cross Section from 3 to 450 keV
R. L. Macklin
Nuclear Science and Engineering | Volume 59 | Number 3 | March 1976 | Pages 231-236
Technical Paper | doi.org/10.13182/NSE76-A26821
Spectra of Bremsstrahlung Produced in Very Thick Lead Targets by 15-, 20-, and 25-MeV Electrons
Takashi Nakamura, Hideo Hirayama
Nuclear Science and Engineering | Volume 59 | Number 3 | March 1976 | Pages 237-245
Technical Paper | doi.org/10.13182/NSE76-A26822
Moments Method Calculation of the Energy-Dependent Neutron Flux Due to a Point-lsotropic Fission Source in an Infinite Medium of Sodium
E. E. Morris
Nuclear Science and Engineering | Volume 59 | Number 3 | March 1976 | Pages 246-260
Technical Paper | doi.org/10.13182/NSE76-A26823
Effect of Anisotropy in Scattering on Neutron Angular Flux Inside Slabs
Lakshmi Rangaswamy, L. S. Kothari, Feroz Ahmed
Nuclear Science and Engineering | Volume 59 | Number 3 | March 1976 | Pages 261-270
Technical Paper | doi.org/10.13182/NSE76-A26824
Accuracy of the Quasistatic Method for Two-Dimensional Thermal Reactor Transients with Feedback
H. L. Dodds, Jr.
Nuclear Science and Engineering | Volume 59 | Number 3 | March 1976 | Pages 271-276
Technical Note | doi.org/10.13182/NSE76-A26825
Incorporation of Spectral Effects into One-Group Nodal Simulators
Martin Becker
Nuclear Science and Engineering | Volume 59 | Number 3 | March 1976 | Pages 276-278
Technical Note | doi.org/10.13182/NSE76-A26826
Anisotropic Neutron Transport Without Legendre Expansions
J. P. Odom, J. K. Shultis
Nuclear Science and Engineering | Volume 59 | Number 3 | March 1976 | Pages 278-281
Technical Note | doi.org/10.13182/NSE76-5

Number 4

Table of Contents
Comments on “A New Definition of the Cell Diffusion Coefficient” (Riccardo A. Bonalumi)
Comments on “Systems with Stochastic Parameters” (M. M. R. Williams)
Rejoinder to “Comments on ‘Systems with Stochastic Parameters’” (Karmeshu N. K. Bansal)

Multidimensional Space-Time Nuclear-Reactor Kinetics Studies—Part I: Theoretical
M. R. Buckner and J. W. Stewart
Nuclear Science and Engineering | Volume 59 | Number 4 | April 1976 | Pages 289-297
Technical Paper | doi.org/10.13182/NSE59-289
Multidimensional Space-Time Nuclear-Reactor Kinetics Studies—Part II: Experimental
P. B. Parks, N. P. Baumann, R. L. Currie, and C. E. Jewell
Nuclear Science and Engineering | Volume 59 | Number 4 | April 1976 | Pages 298-310
Technical Paper | doi.org/10.13182/NSE76-A26832
A Tensor Transformation Technique for the Transport Equation
S. L. Gralnick
Nuclear Science and Engineering | Volume 59 | Number 4 | April 1976 | Pages 311-318
Technical Paper | doi.org/10.13182/NSE76-A26833
A New Expansion for Highly Anisotropic Neutron-Nucleus Scattering
E. A. Attia and A. A. Harms
Nuclear Science and Engineering | Volume 59 | Number 4 | April 1976 | Pages 319-325
Technical Paper | doi.org/10.13182/NSE76-6
Application of Coarse-Mesh Rebalance Acceleration to Monte Carlo Eigenvalue Problems
T. Asaoka, Y. Nakahara, K. Horikami, T. Nishida, T. Suzuki, Y. Taji, S. Miyasaka, and J. Hirota
Nuclear Science and Engineering | Volume 59 | Number 4 | April 1976 | Pages 326-336
Technical Paper | doi.org/10.13182/NSE76-A26835
Thermal-Reactor Lattice Analysis Using ENDF/B-IV Data with Monte Carlo Resonance Reaction Rates
W. Rothenstein
Nuclear Science and Engineering | Volume 59 | Number 4 | April 1976 | Pages 337-349
Technical Paper | doi.org/10.13182/NSE76-A26836
Reactivity Surveillance Experiments with the Engineering Mock-Up Core of the Fast Flux Test Facility Reactor
J. T. Mihalczo, M. V. Mathis, and V. K. Paré
Nuclear Science and Engineering | Volume 59 | Number 4 | April 1976 | Pages 350-368
Technical Paper | doi.org/10.13182/NSE76-A26837
An On-Line Reactor Surveillance Algorithm Based on Multivariate Analysis of Noise
K. R. Piety and J. C. Robinson
Nuclear Science and Engineering | Volume 59 | Number 4 | April 1976 | Pages 369-380
Technical Paper | doi.org/10.13182/NSE76-A26838
Neutron Capture Cross Sections from 0.1 to 3 MeV by Activation Measurements
M. Lindner, R. J. Nagle, and J. H. Landrum
Nuclear Science and Engineering | Volume 59 | Number 4 | April 1976 | Pages 381-394
Technical Paper | doi.org/10.13182/NSE76-2
Energy Spectra of Secondary Neutrons from the ²³⁸U(n, 2n) and (n, 3n) Reactions
M. Caner, M. Segev, S. Yiftah
Nuclear Science and Engineering | Volume 59 | Number 4 | April 1976 | Pages 395-405
Technical Paper | doi.org/10.13182/NSE76-A26840
The Transport of Radioactive Corrosion Products in High-Temperature Water II. The Activation of Isothermal Steel Surfaces
D. H. Lister
Nuclear Science and Engineering | Volume 59 | Number 4 | April 1976 | Pages 406-426
Technical Paper | doi.org/10.13182/NSE76-7
A New Direct Point Flux Monte Carlo Estimator Using Compensated Rotational Symmetry
Y. S. Horowitz, A. Dubi, and S. Mordechai
Nuclear Science and Engineering | Volume 59 | Number 4 | April 1976 | Pages 427-429
Technical Note | doi.org/10.13182/NSE76-A26842
Energy Group Structures and Minimum Critical Mass
Richard B. Jones and P. F. Zweifel
Nuclear Science and Engineering | Volume 59 | Number 4 | April 1976 | Pages 429-436
Technical Note | doi.org/10.13182/NSE76-A26843
Subcritical Reactivity from Polarity Correlation
Tai-Ping Lung and Lawrence Ruby
Nuclear Science and Engineering | Volume 59 | Number 4 | April 1976 | Pages 436-440
Technical Note | doi.org/10.13182/NSE76-A26844
Limits on Sodium Voiding Reactivity Addition Rate for Very Large Liquid-Metal Fast Breeder Reactors
H. H. Hummel, Kalimullah, and P. Pizzica
Nuclear Science and Engineering | Volume 59 | Number 4 | April 1976 | Pages 440-441
Technical Note | doi.org/10.13182/NSE76-A26845
Alternative Materials for Microfission Target Pellets
James H. Renken
Nuclear Science and Engineering | Volume 59 | Number 4 | April 1976 | Pages 442-444
Technical Note | doi.org/10.13182/NSE76-A26846