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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 | 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

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 | 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

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 | 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

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 | 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