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Volume 64

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Number 1

Table of Contents
A Philosophical Peregrination Through Benchmark Park(R. A. Dannels)

Preface: Improved Methods for Analysis of Nuclear Systems

Kaye D. Lathrop, Chairman

Nuclear Science and Engineering / Volume 64 / Number 1 / September 1977 / Page 1

Preface / dx.doi.org/10.13182/NSE77-A27071

Tokamak Transport Simulation Models

John T. Hogan

Nuclear Science and Engineering / Volume 64 / Number 1 / September 1977 / Pages 2-17

Technical Paper / dx.doi.org/10.13182/NSE77-A27072

Computation of Magnetohydrodynamic Flow in a Magnetically Confined Plasma

D. C. Barnes, J. U. Brackbill

Nuclear Science and Engineering / Volume 64 / Number 1 / September 1977 / Pages 18-32

Technical Paper / dx.doi.org/10.13182/NSE77-A27073

Velocity-Space Methods for Fusion Reactor Plasmas

Niels K. Winsor

Nuclear Science and Engineering / Volume 64 / Number 1 / September 1977 / Pages 33-40

Technical Paper / dx.doi.org/10.13182/NSE77-A27074

Particle Simulation Models and Their Application to Controlled Fusion

H. Okuda

Nuclear Science and Engineering / Volume 64 / Number 1 / September 1977 / Pages 41-48

Technical Paper / dx.doi.org/10.13182/NSE77-A27075

Laser Fusion Hydrodynamics Calculations

Gregory A. Moses

Nuclear Science and Engineering / Volume 64 / Number 1 / September 1977 / Pages 49-63

Technical Paper / dx.doi.org/10.13182/NSE77-A27076

Computational Benchmark Problems—A Review of Recent Work Within the American Nuclear Society Mathematics and Computation Division

H. L. Dodds, Jr.

Nuclear Science and Engineering / Volume 64 / Number 1 / September 1977 / Pages 64-73

Technical Paper / dx.doi.org/10.13182/NSE77-A27077

Benchmark Calculations for a Sodium-Cooled Breeder Reactor by Two- and Three-Dimensional Diffusion Methods

G. Buckel, K. Küfner, B. Stehle

Nuclear Science and Engineering / Volume 64 / Number 1 / September 1977 / Pages 75-89

Technical Paper / dx.doi.org/10.13182/NSE77-A27079

Benchmark Analysis of Liquid-Metal Fast Breeder Reactor Nuclear Design Methods

E. Kujawski, H. S. Bailey

Nuclear Science and Engineering / Volume 64 / Number 1 / September 1977 / Pages 90-94

Technical Paper / dx.doi.org/10.13182/NSE77-A27080

CANDU Reactor Kinetics Benchmark Activity

F. N. McDonnell, A. P. Baudouin, P. M. Garvey, J. C. Luxat

Nuclear Science and Engineering / Volume 64 / Number 1 / September 1977 / Pages 95-105

Technical Paper / dx.doi.org/10.13182/NSE77-A27081

Numerical Standards for Flow-Boiling Analysis

W. T. Hancox, S. Banerjee

Nuclear Science and Engineering / Volume 64 / Number 1 / September 1977 / Pages 106-123

Technical Paper / dx.doi.org/10.13182/NSE77-A27082

New Areas for Benchmark Computation

E. M. Gelbard, H. Henryson II

Nuclear Science and Engineering / Volume 64 / Number 1 / September 1977 / Pages 124-131

Technical Paper / dx.doi.org/10.13182/NSE77-A27083

Two-Dimensional Finite Element Calculational Methods for Plasma Diffusion in Low-Beta Devices

R. England, J. P. Hennart, J. G. Martin, L. Melendez L., S. M. Waller

Nuclear Science and Engineering / Volume 64 / Number 1 / September 1977 / Pages 132-140

Technical Paper / dx.doi.org/10.13182/NSE77-A27084

Fluid Simulation of Large Tokamak Plasmas Using a Variable Spatial Mesh, Variable Time-Step Implicit Procedure

Wayne A. Houlberg, Robert W. Conn

Nuclear Science and Engineering / Volume 64 / Number 1 / September 1977 / Pages 141-150

Technical Paper / dx.doi.org/10.13182/NSE77-A27085

New Techniques for Studying Some Effects of Suprathermal Alpha Particles

T. W. Petrie, G. H. Miley

Nuclear Science and Engineering / Volume 64 / Number 1 / September 1977 / Pages 151-162

Technical Paper / dx.doi.org/10.13182/NSE77-A27086

Growth and Saturation of Instability of Spherical Implosions Driven by Laser or Charged Particle Beams

R. L. McCrory, R. L. Morse, K. A. Taggart

Nuclear Science and Engineering / Volume 64 / Number 1 / September 1977 / Pages 163-176

Technical Paper / dx.doi.org/10.13182/NSE77-A27087

A Finite Difference Method for Thermally Expandable Fluid Transients

T. A. Porsching

Nuclear Science and Engineering / Volume 64 / Number 1 / September 1977 / Pages 177-186

Technical Paper / dx.doi.org/10.13182/NSE77-A27088

Computing a Two-Dimensional Quench Front

D. Durack, B. Wendroff

Nuclear Science and Engineering / Volume 64 / Number 1 / September 1977 / Pages 187-191

Technical Paper / dx.doi.org/10.13182/NSE77-A27089

A Local Green's Function Method for the Numerical Solution of Heat Conduction and Fluid Flow Problems

William C. Horak, J. J. Dorning

Nuclear Science and Engineering / Volume 64 / Number 1 / September 1977 / Pages 192-207

Technical Paper / dx.doi.org/10.13182/NSE77-A27090

Efficient High-Order Method for the Solution of Fluid Dynamics Equations

P. Romstedt, W. Werner

Nuclear Science and Engineering / Volume 64 / Number 1 / September 1977 / Pages 208-218

Technical Paper / dx.doi.org/10.13182/NSE77-A27091

Prospects for Accurate Computer Simulations of Fluid Dynamics Problems of Nuclear Reactors

Patrick J. Roache

Nuclear Science and Engineering / Volume 64 / Number 1 / September 1977 / Pages 219-221

Technical Paper / dx.doi.org/10.13182/NSE77-A27092

An Efficient Multidimensional Numerical Method for the Thermal-Hydraulic Analysis of Nuclear Reactor Cores

Robert E. Masterson, Lothar Wolf

Nuclear Science and Engineering / Volume 64 / Number 1 / September 1977 / Pages 222-236

Technical Paper / dx.doi.org/10.13182/NSE77-A27093

A Eulerian Computation Method for Fluid Flows with Large Density Gradients at All Speeds

C. W. Stewart, T. L. George

Nuclear Science and Engineering / Volume 64 / Number 1 / September 1977 / Pages 237-243

Technical Paper / dx.doi.org/10.13182/NSE77-A27094

Three-Dimensional Thermal-Hydraulic Analysis of Wire-Wrapped Rods in Liquid-Metal Fast Breeder Reactor Core Assemblies

M. C. Chuang, M. D. Carelli, C. W. Bach, J. S. Killimayer

Nuclear Science and Engineering / Volume 64 / Number 1 / September 1977 / Pages 244-257

Technical Paper / dx.doi.org/10.13182/NSE77-A27095

Comparison of Two Uncertainty Analysis Methods

Neil D. Cox

Nuclear Science and Engineering / Volume 64 / Number 1 / September 1977 / Pages 258-265

Technical Paper / dx.doi.org/10.13182/NSE77-A27096

Fission Product Release Calculations from a Reactor Containment Building

Clarence E. Lee, Courtney E. Apperson, Jr., John E. Foley

Nuclear Science and Engineering / Volume 64 / Number 1 / September 1977 / Pages 266-275

Technical Paper / dx.doi.org/10.13182/NSE77-A27097

Optimum Design of Loss-of-Coolant-Accident Codes Panel Discussion

H. C. Honeck, G. A. Mortensen, W. H. Reed, K. Richert, R. J. Wagner, Wolfgang Wulff

Nuclear Science and Engineering / Volume 64 / Number 1 / September 1977 / Pages 276-277

Technical Paper / dx.doi.org/10.13182/NSE77-A27098

Number 2

Table of Contents

Progress in Multidimensional Neutron Transport Computation

E. E. Lewis

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 279-293

Technical Paper / dx.doi.org/10.13182/NSE77-A27370

Neutron Transport Methods in Neutrino Transport Calculations

S. A. Bludman, I. Lichtenshtadt, A. Ron, N. Sack, J. J. Wagschal

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 294-298

Technical Paper / dx.doi.org/10.13182/NSE77-A27371

Compatible Product Angular Quadrature for Neutron Transport in x-y Geometry

I. K. Abu-Shumays

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 299-316

Technical Paper / dx.doi.org/10.13182/NSE64-299

The Generation of Time-Dependent Neutron Transport Solutions in Infinite Media

B. D. Ganapol, P. W. McKenty, K. L. Peddicord

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 317-331

Technical Paper / dx.doi.org/10.13182/NSE77-A27373

Application of Space-Angle Synthesis to Two-Dimensional Neutral-Particle Transport Problems of Weapon Physics

Richard M. Roberds, Charles J. Bridgman

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 332-343

Technical Paper / dx.doi.org/10.13182/NSE77-A27374

Diffusion Synthetic Acceleration Methods for the Diamond-Differenced Discrete-Ordinates Equations

R. E. Alcouffe

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 344-355

Technical Paper / dx.doi.org/10.13182/NSE77-1

The Direct-Coupled-Ray Method for Design-Oriented Three-Dimensional Transport Analysis

James A. Bucholz, Claude G. Poncelet

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 356-372

Technical Paper / dx.doi.org/10.13182/NSE77-A27376

Ray Tracing in Axisymmetric Toroidal Coordinates

S. L. Gralnick, H. E. Dalhed

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 373-378

Technical Paper / dx.doi.org/10.13182/NSE77-A27377

Charged Particle Energy Deposition in an Inertially Confined Thermonuclear Plasma

Michael J. Antal, Clarence E. Lee

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 379-383

Technical Paper / dx.doi.org/10.13182/NSE77-A27378

Approximate Solutions of the Two-Dimensional Integral Transport Equation by Collision Probability Methods

Richard Sanchez

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 384-404

Technical Paper / dx.doi.org/10.13182/NSE64-384

Nodal Coupling by Response Matrix Principles

A. Ancona, M. Becker, M. D. Beg, D. R. Harris, A. DaC. Menezes, D. M. VerPlanck, E. Pilat

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 405-417

Technical Paper / dx.doi.org/10.13182/NSE77-A27380

Mathematical and Computational Techniques Employed in the Deterministic Approach to Liquid-Metal Fast Breeder Reactor Safety

Alan E. Waltar, Andrew Padilla, Jr.

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 418-451

Technical Paper / dx.doi.org/10.13182/NSE77-A27381

Probabilistic Fast Reactor Accident Analysis

Karl O. Ott

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 452-464

Technical Paper / dx.doi.org/10.13182/NSE77-A27382

A Numerical Model of Reactor Fuel and Coolant Motions Following Pin Failure

P. A. Pizzica, P. B. Abramson

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 465-479

Technical Paper / dx.doi.org/10.13182/NSE77-A27383

Simulation of Transients in Liquid-Metal Fast Breeder Reactor Systems

A. K. Agrawal, J. G. Guppy, I. K. Madni, V. Quan, W. L. Weaver III, J. W. Yang

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 480-491

Technical Paper / dx.doi.org/10.13182/NSE77-A27384

Smoothing and Extrapolation Techniques for Reactor Kinetics

R. D. Lawrence, J. J. Dorning

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 492-507

Technical Paper / dx.doi.org/10.13182/NSE77-A27385

High-Order Schemes for Neutron Kinetics Calculations, Based on a Local Polynomial Approximation

S. Langenbuch, W. Maurer, W. Werner

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 508-516

Technical Paper / dx.doi.org/10.13182/NSE77-A27386

Conservation of the Adjoint Neutron Spectrum by Use of Bilinear-Weighted Cross Sections and Its Effect on Fast Reactor Calculations

D. C. Wade, R. G. Bucher

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 517-538

Technical Paper / dx.doi.org/10.13182/NSE77-A27387

Method for Generating Neutronic Data Bases for Transient Reactor Calculations

M. R. Buckner, P. B. Parks

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 539-551

Technical Paper / dx.doi.org/10.13182/NSE77-A27388

Current Trends in Methods for Neutron Diffusion Calculations

C. H. Adams

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 552-562

Technical Paper / dx.doi.org/10.13182/NSE77-A27389

A Finite Element Depletion Diffusion Calculation Method with Space-Dependent Cross Sections

Alain Kavenoky, Jean-Jacques Lautard

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 563-575

Technical Paper / dx.doi.org/10.13182/NSE77-A27390

The Energy-Dependent Finite Element Method for Two-Dimensional Diffusion Problems

Hideko Komoriya, Wallace F. Walters

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 576-581

Technical Paper / dx.doi.org/10.13182/NSE77-A27391

Two Nodal Methods for Solving Time-Dependent Group Diffusion Equations

R. A. Shober, R. N. Sims, A. F. Henry

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 582-592

Technical Paper / dx.doi.org/10.13182/NSE77-A27392

Optimized Iteration Strategies and Data Management Considerations for Fast Reactor Finite Difference Diffusion Theory Codes

D. R. Ferguson, K. L. Derstine

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 593-604

Technical Paper / dx.doi.org/10.13182/NSE77-5

Theory, Capabilities, and Use of the Three-Dimensional Reactor Operation and Control Simulator (ROCS)

T. G. Ober, J. C. Stork, I. C. Rickard, J. K. Gasper

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 605-623

Technical Paper / dx.doi.org/10.13182/NSE77-A27394

Calculations of Void Streaming in the Argonne Gas-Cooled Fast Reactor Critical Experiments

E. M. Gelbard, D. C. Wade, R. W. Schaefer, R. E. Phillips

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 624-637

Technical Paper / dx.doi.org/10.13182/NSE77-A27395

Convergence Results and Asymptotic Error Estimates for Galerkin-Type Spectral Synthesis

Paul Nelson, Harold D. Meyer

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 638-643

Technical Paper / dx.doi.org/10.13182/NSE77-A27396

Methods for Identification of Dynamic Systems

B. Frogner, B. Friedlander, H. S. Rao

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 644-656

Technical Paper / dx.doi.org/10.13182/NSE77-A27397

Spatial Reactor Control Methods

Jorma Karppinen

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 657-672

Technical Paper / dx.doi.org/10.13182/NSE77-A27398

Identification of Nuclear Plant Parameters Using Experimental Data and High-Order Dynamic Models

S. I. Chang, T. W. Kerlin

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 673-683

Technical Paper / dx.doi.org/10.13182/NSE77-A27399

Reactor Fuel Reliability Constraints on Power Shape Control

Floyd Gelhaus, John Hallam, Tor Sauar

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 684-693

Technical Paper / dx.doi.org/10.13182/NSE77-A27400

Optimal Pin Enrichment Distributions in Boiling Water Reactor Fuel Bundles

E. Y. Lim, A. Leonard

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 694-708

Technical Paper / dx.doi.org/10.13182/NSE77-A27401

Number 3

Table of Contents
Computer Code Abstract
Comments on “The Concept of Spatial Channel Theory Applied to Reactor Shielding Analysis”(S. A. W. Gerstl)
Response to “Comments on ‘The Concept of Spatial Channel Theory Applied to Reactor Shielding Analysis’”(M. L. Williams)
Optimized Taylor Parameters for Concrete Buildup Factor Data(A. B. Chilton)
Comment on “Optimized Taylor Parameters for Concrete Buildup Factor Data”(K. Shure, O. J. Wallace)
Applications of Energy: Nineteenth Century(Alvin M. Weinberg)
Boiling Liquid-Metal Heat Transfer(S. George Bankoff, H. K. Fauske)
Statistical Energy Analysis of Dynamical Systems: Theory and Applications(Raymond M. Brach)
Elements of Nuclear Reactor Design(J. K. Shultis)

Internal Pressurization in Solid Mixed-Oxide Fuel Due to Transient Fission Gas Release

J. R. Hofmann, C. C. Meek

Nuclear Science and Engineering / Volume 64 / Number 3 / November 1977 / Pages 713-723

Technical Paper / dx.doi.org/10.13182/NSE77-A27100

Convergence and Acceleration of Void Iterations in Boiling Water Reactor Core Calculations

Makoto Tsuiki, Katsutada Aoki, Sadanori Yoshimura

Nuclear Science and Engineering / Volume 64 / Number 3 / November 1977 / Pages 724-732

Technical Paper / dx.doi.org/10.13182/NSE77-A27101

Fast-Neutron Cross Sections of Vanadium

P. Guenther, D. Havel, A. Smith, J. Whalen

Nuclear Science and Engineering / Volume 64 / Number 3 / November 1977 / Pages 733-743

Technical Paper / dx.doi.org/10.13182/NSE77-A27102

The Neutron Capture Cross Section of Yttrium-89

J. W. Boldeman, B. J. Allen, A. R. de L. Musgrove, R. L. Macklin

Nuclear Science and Engineering / Volume 64 / Number 3 / November 1977 / Pages 744-748

Technical Paper / dx.doi.org/10.13182/NSE77-A27103

Energy Spectra of Delayed Neutrons from the Precursors ⁷⁹(Zn, Ga), ⁸⁰Ga, ⁸¹Ga, ⁹⁴Rb, ⁹⁵Rb, ¹²⁹In, and ¹³⁰In

G. Rudstam, E. Lund

Nuclear Science and Engineering / Volume 64 / Number 3 / November 1977 / Pages 749-760

Technical Paper / dx.doi.org/10.13182/NSE77-A27104

Transport Calculations of Neutron Wave Experiments in Subcritical Assemblies

F. C. Difilippo

Nuclear Science and Engineering / Volume 64 / Number 3 / November 1977 / Pages 761-767

Technical Paper / dx.doi.org/10.13182/NSE77-A27105

A Finite Element Code for Time-Dependent Plasma Diffusion in Arbitrary Toroidal Geometry

J. P. Hennart, J. G. Martín, J. Sánchez G.

Nuclear Science and Engineering / Volume 64 / Number 3 / November 1977 / Pages 768-778

Technical Paper / dx.doi.org/10.13182/NSE77-A27106

Approximated Space-Energy Resolution of Fast-Neutron Fluxes

B. Rocca-Volmerange

Nuclear Science and Engineering / Volume 64 / Number 3 / November 1977 / Pages 779-784

Technical Note / dx.doi.org/10.13182/NSE77-A27107

Gamma-Ray Emission Probabilities in the Decay of Barium-140 and Lanthanum-140

K. Debertin, U. Schötzig, K. F. Walz

Nuclear Science and Engineering / Volume 64 / Number 3 / November 1977 / Pages 784-786

Technical Note / dx.doi.org/10.13182/NSE77-A27108

Neutron Resonance Heterogeneity Effect in the Vicinity of a Gross Region Interface

Yukio Ishiguro, Akira Hasegawa

Nuclear Science and Engineering / Volume 64 / Number 3 / November 1977 / Pages 786-791

Technical Note / dx.doi.org/10.13182/NSE77-A27109

Symmetry Reduction of Reactor Systems

R. Nieva, G. S. Christensen

Nuclear Science and Engineering / Volume 64 / Number 3 / November 1977 / Pages 791-795

Technical Note / dx.doi.org/10.13182/NSE77-A27110

Number 4

Table of Contents
Book Review - Reactor Core Fuel Management(Ryohei Kiyose)
Book Review - EMP Radiation and Protective Techniques(P. R. Barnes)
Corrigendum(S. B. Gunst, D. E. Conway, J. C. Connor)

A Generalized Perturbation Theory Applicable to Reactor Boundary Changes

Masaoki Komata

Nuclear Science and Engineering / Volume 64 / Number 4 / December 1977 / Pages 811-822

Technical Paper / dx.doi.org/10.13182/NSE77-A14496

Anisotropy of Scattering and Fission in Neutron Transport Theory

V. C. Boffi, V. G. Molinari, G. Spiga

Nuclear Science and Engineering / Volume 64 / Number 4 / December 1977 / Pages 823-836

Technical Paper / dx.doi.org/10.13182/NSE77-A14497

Angular Biasing of the Collision Process in Multigroup Monte Carlo Calculations

J. S. Tang, T. J. Hoffman, P. N. Stevens

Nuclear Science and Engineering / Volume 64 / Number 4 / December 1977 / Pages 837-842

Technical Paper / dx.doi.org/10.13182/NSE77-A14498

The Significance of Fast Moderator Feedback Effects in a Boiling Water Reactor During Severe Pressure Transients

W. Frisch, S. Langenbuch, P. Peternell

Nuclear Science and Engineering / Volume 64 / Number 4 / December 1977 / Pages 843-848

Technical Paper / dx.doi.org/10.13182/NSE77-A14499

²³²Th(n,γ) Cross Section from 2.6 to 800 keV

R. L. Macklin, J. Halperin

Nuclear Science and Engineering / Volume 64 / Number 4 / December 1977 / Pages 849-858

Technical Paper / dx.doi.org/10.13182/NSE77-A14500

The Influence of Isomeric States on Independent Fission Product Yields

David G. Madland, Talmadge R. England

Nuclear Science and Engineering / Volume 64 / Number 4 / December 1977 / Pages 859-865

Technical Paper / dx.doi.org/10.13182/NSE77-A14501

The Solubility of Nonstoichiometric Nickel Ferrite in High-Temperature Aqueous Solution

Y. L. Sandler, R. H. Kunig

Nuclear Science and Engineering / Volume 64 / Number 4 / December 1977 / Pages 866-874

Technical Paper / dx.doi.org/10.13182/NSE77-A14502

Piecewise Polynomial Approximations for Nuclear Reactor Point and Space Kinetics

J. P. Hennart

Nuclear Science and Engineering / Volume 64 / Number 4 / December 1977 / Pages 875-882

Technical Note / dx.doi.org/10.13182/NSE77-A14503

Closed-Form Solutions for Some Two-Group Problems with Anisotropic Scattering

C. Cercignani

Nuclear Science and Engineering / Volume 64 / Number 4 / December 1977 / Pages 882-884

Technical Note / dx.doi.org/10.13182/NSE77-A14504

Flux-Depression Factors for Scattering and Absorbing Media

C. E. Siewert, K. Neshat, J. S. Phelps III

Nuclear Science and Engineering / Volume 64 / Number 4 / December 1977 / Pages 884-886

Technical Note / dx.doi.org/10.13182/NSE77-A14505

The Effect of the Azimuthal Angle on Fast-Neutron Concrete Albedos

William H. Miller, Walter Meyer

Nuclear Science and Engineering / Volume 64 / Number 4 / December 1977 / Pages 886-889

Technical Note / dx.doi.org/10.13182/NSE77-A14506

On the Systematic Errors of the Determination of the Cadmium Ratio of Neutron Capture Rates in Slightly Enriched Uranium

Çetin Ertek

Nuclear Science and Engineering / Volume 64 / Number 4 / December 1977 / Pages 889-892

Technical Note / dx.doi.org/10.13182/NSE77-A14507

Precise Uranium-235 Fission Cross-Section Measurements Below 1 keV

J. B. Czirr, G. W. Carlson

Nuclear Science and Engineering / Volume 64 / Number 4 / December 1977 / Pages 892-894

Technical Note / dx.doi.org/10.13182/NSE77-A14508

Additional Measurements of the ²³⁵(n, f) Cross Section in the 0.2- to 8.2-MeV Range

W. P. Poenitz

Nuclear Science and Engineering / Volume 64 / Number 4 / December 1977 / Pages 894-897

Technical Note / dx.doi.org/10.13182/NSE77-A14509

Measurement of Cross Sections for the ²³Na(n, n′γ)²³Na Reaction near Threshold

Donald L. Smith

Nuclear Science and Engineering / Volume 64 / Number 4 / December 1977 / Pages 897-901

Technical Note / dx.doi.org/10.13182/NSE77-A14510