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Volume 59

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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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NSE76-A26813

Number 2

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

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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NSE76-A26846