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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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NSE77-A27098
Progress in Multidimensional Neutron Transport Computation
E. E. Lewis
Nuclear Science and Engineering | Volume 64 | Number 2 | October 1977 | Pages 279-293
Technical Paper | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NSE77-A27401
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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NSE77-A27110
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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NSE77-A14510