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Discrete Ordinate Neutron Transport Equation Equivalent to PL Approximation
Jungchung Jung, Hiroshi Chijiwa, Keisuke Kobayashi,Hiroshi Nishihara
Nuclear Science and Engineering | Volume 49 | Number 1 | September 1972 | Pages 1-9
Technical Paper | doi.org/10.13182/NSE49-01-01
Spherical Harmonic Solutions of the Neutron Transport Equation from Discrete Ordinate Codes
Wm. H. Reed
Nuclear Science and Engineering | Volume 49 | Number 1 | September 1972 | Pages 10-19
Technical Paper | doi.org/10.13182/NSE72-A22523
Effect of Singularities on Approximation in SN Methods
Jacek Arkuszewski, Teresa Kulikowska, Janusz Mika
Nuclear Science and Engineering | Volume 49 | Number 1 | September 1972 | Pages 20-26
Technical Paper | doi.org/10.13182/NSE72-4
A Timing Comparison Study for Some High Order Finite Element Approximation Procedures and a Low Order Finite Difference Approximation Procedure for the Numerical Solution of the Multigroup Neutron Diffusion Equation
Hans G. Kaper, Gary K. Leaf, Arthur J. Lindeman
Nuclear Science and Engineering | Volume 49 | Number 1 | September 1972 | Pages 27-48
Technical Paper | doi.org/10.13182/NSE72-A22525
Spherical Harmonics Treatment of Epithermal Neutron Spectra in Reactor Lattices
M. V. Mataušek
Nuclear Science and Engineering | Volume 49 | Number 1 | September 1972 | Pages 49-58
Technical Paper | doi.org/10.13182/NSE72-A22526
In-Core Fuel Management Optimization by Heuristic Learning Technique
Tsutomu Hoshino*
Nuclear Science and Engineering | Volume 49 | Number 1 | September 1972 | Pages 59-71
Technical Paper | doi.org/10.13182/NSE72-A22527
The Yield Stress Radiation Damage Function of Iron
G. R. Odette, T. O. Ziebold
Nuclear Science and Engineering | Volume 49 | Number 1 | September 1972 | Pages 72-81
Technical Paper | doi.org/10.13182/NSE72-A22528
Monte Carlo Calculations of High-Energy Nucleon-Meson Cascades and Comparison with Experiment
T. W. Armstrong, R. G. Alsmiller, Jr., K. C. Chandler, B. L. Bishop
Nuclear Science and Engineering | Volume 49 | Number 1 | September 1972 | Pages 82-92
Technical Paper | doi.org/10.13182/NSE72-A22529
A Numerical Calculation of the Redistribution of an Interstitial Solute in a Thermal Gradient
G. P. Marino
Nuclear Science and Engineering | Volume 49 | Number 1 | September 1972 | Pages 93-98
Technical Paper | doi.org/10.13182/NSE72-A22530
Linear Stability of Fast and Thermal Reactor Models Using Space-Time Kinetics
Kenneth Alvin Solomon and William E. Kastenberg
Nuclear Science and Engineering | Volume 49 | Number 1 | September 1972 | Pages 99-103
Technical Note | doi.org/10.13182/NSE72-A22531
Experimentally Measured Dose Albedos of Intermediate Energy Bremsstrahlung
Thomas R. Crites
Nuclear Science and Engineering | Volume 49 | Number 1 | September 1972 | Pages 103-106
Technical Note | doi.org/10.13182/NSE72-A22532
Hot Spot Expectation in Nuclear Reactor Core Thermal Design
A. Amendola
Nuclear Science and Engineering | Volume 49 | Number 1 | September 1972 | Pages 106-108
Technical Note | doi.org/10.13182/NSE72-A22533
Inverse Compton Scattering as an Energy Loss Mechanism in a Controlled Thermonuclear Reactor
Paul A. Robinson, Jr., George D. Sauter
Nuclear Science and Engineering | Volume 49 | Number 2 | October 1972 | Pages 117-129
Technical Paper | doi.org/10.13182/NSE72-A35500
Neutron Displacement Cross Sections for Stainless Steel and Tantalum Based on a Lindhard Model
D. G. Doran
Nuclear Science and Engineering | Volume 49 | Number 2 | October 1972 | Pages 130-144
Technical Paper | doi.org/10.13182/NSE72-A35501
The Total Neutron Cross Sections of the Curium Isotopes from 0.01 to 30 eV
J. R. Berreth, F. B. Simpson, B. C. Rusche
Nuclear Science and Engineering | Volume 49 | Number 2 | October 1972 | Pages 145-152
Technical Paper | doi.org/10.13182/NSE72-A35502
Neutron Capture, Fission, and Total Cross Sections of Plutonium-240 from 20 eV to 30 keV
R. W. Hockenbury, W. R. Moyer, R. C. Block
Nuclear Science and Engineering | Volume 49 | Number 2 | October 1972 | Pages 153-161
Technical Paper | doi.org/10.13182/NSE72-A35503
Neutron Angular Distribution Analysis Using Cylindrical Bessel Functions
S. Pearlstein
Nuclear Science and Engineering | Volume 49 | Number 2 | October 1972 | Pages 162-171
Technical Paper | doi.org/10.13182/NSE72-A35504
On the Application of Eigenfunction Expansions to Problems in Nonlinear Space-Time Reactor Dynamics
Edmund T. Rumble, III, William E. Kastenberg
Nuclear Science and Engineering | Volume 49 | Number 2 | October 1972 | Pages 172-187
Technical Paper | doi.org/10.13182/NSE72-A35505
Local Nuclear Reactor Power Measurements Using Gamma-Ray Fluctuations
F. E. LeVert, M. A. Schultz
Nuclear Science and Engineering | Volume 49 | Number 2 | October 1972 | Pages 188-201
Technical Paper | doi.org/10.13182/NSE72-A35506
A Two Overlapping-Group Transport Computational Method for Thermal Neutron Problems
M. Natelson, E. M. Gelbard
Nuclear Science and Engineering | Volume 49 | Number 2 | October 1972 | Pages 202-212
Technical Paper | doi.org/10.13182/NSE72-A35507
An Improved Reactivity Table Model for Liquid Metal Fast Breeder Reactor Dynamics
Weston M. Stacey, Jr.
Nuclear Science and Engineering | Volume 49 | Number 2 | October 1972 | Pages 213-227
Technical Paper | doi.org/10.13182/NSE72-A35508
An Analysis of the Doppler Effect of Structural Materials
Yukio Ishiguro
Nuclear Science and Engineering | Volume 49 | Number 2 | October 1972 | Pages 228-232
Technical Note | doi.org/10.13182/NSE72-A35509
The Neutron Spectrum from a Fission Source in Water
A. E. Profio, R. J. Cerbone, D. L. Huffman
Nuclear Science and Engineering | Volume 49 | Number 2 | October 1972 | Pages 232-236
Technical Note | doi.org/10.13182/NSE72-A35510
Measurements of the Effective Delayed-Neutron Fraction in Two Fast Critical Experiments
S. G. Carpenter, J. M. Gasidlo, J. M. Stevenson
Nuclear Science and Engineering | Volume 49 | Number 2 | October 1972 | Pages 236-239
Technical Note | doi.org/10.13182/NSE72-2
A Simple Computational Model for Rod Motion Transients
D. J. Diamond, G. S. Lellouche, M. M. Levine
Nuclear Science and Engineering | Volume 49 | Number 2 | October 1972 | Pages 239-243
Technical Note | doi.org/10.13182/NSE72-A35512
Tritium Generation in the Coolant-Moderator of Pressurized Water Reactors
Karl Hornyik
Nuclear Science and Engineering | Volume 49 | Number 3 | November 1972 | Pages 247-254
Technical Paper | doi.org/10.13182/NSE72-A22539
Optimum Binary Signals for Reactor Frequency Response Measurements
M. R. Buckner, T. W. Kerlin
Nuclear Science and Engineering | Volume 49 | Number 3 | November 1972 | Pages 255-262
Technical Paper | doi.org/10.13182/NSE72-A22540
Minimum Critical Mass in Intermediate Reactors Subject to Constraints on Power Density and Fuel Enrichment
P. Goldschmidt
Nuclear Science and Engineering | Volume 49 | Number 3 | November 1972 | Pages 263-273
Technical Paper | doi.org/10.13182/NSE72-A22541
Critical Experiments for the Brookhaven Pulsed Fast Reactor Study
J. Phelps, H. Windsor, H. Takahashi, J. Conant, K. Chandramoleswar
Nuclear Science and Engineering | Volume 49 | Number 3 | November 1972 | Pages 274-300
Technical Paper | doi.org/10.13182/NSE72-A22542
The Angular Distribution of Thermal Neutrons at the Surfaces of Black and Grey Cylinders
D. G. Doutriaux, D. G. Andrews
Nuclear Science and Engineering | Volume 49 | Number 3 | November 1972 | Pages 301-309
Technical Paper | doi.org/10.13182/NSE72-A22543
The Ratio of the Uranium-238 to Uranium-235 Fission Cross Sections from 1 to 5 MeV
J. W. Meadows
Nuclear Science and Engineering | Volume 49 | Number 3 | November 1972 | Pages 310-316
Technical Paper | doi.org/10.13182/NSE72-A22544
Neutron Capture Cross Sections in the keV Region for 154Sm, 160Gd, 164Dy, and 165Ho
L. R. Fawcett, Jr., A. Keith Furr, J. G. Lindsay
Nuclear Science and Engineering | Volume 49 | Number 3 | November 1972 | Pages 317-329
Technical Paper | doi.org/10.13182/NSE72-A22545
Measurement and Analysis of Fast Neutron Spectra in Uranium Depleted in the Uranium-235 Isotope
N. N. Kaushal, B. K. Malaviya, M. Becker, E.T. Burns, E. R. Gaerttner
Nuclear Science and Engineering | Volume 49 | Number 3 | November 1972 | Pages 330-348
Technical Paper | doi.org/10.13182/NSE72-A22546
Evaluation of Gamma-Ray Shielding Calculations and Determination of Shielding Parameters with Bremsstrahlung Radiation
L. F. Rodriguez, A. Shapiro
Nuclear Science and Engineering | Volume 49 | Number 3 | November 1972 | Pages 349-357
Technical Paper | doi.org/10.13182/NSE72-A22547
Measurement of the Ratio of the Prompt to the Delayed Neutronic Response of a Self-Powered Vanadium Detector by Cross-Correlation Techniques
W. Seifritz
Nuclear Science and Engineering | Volume 49 | Number 3 | November 1972 | Pages 358-369
Technical Paper | doi.org/10.13182/NSE72-A22548
The Integral Transform Method for the Average Neutron Transport Properties of a Lattice
M. opi
Nuclear Science and Engineering | Volume 49 | Number 3 | November 1972 | Pages 370-376
Technical Note | doi.org/10.13182/NSE72-A22549
Analytical Treatment of Neutron Age in Perpendicular Direction in Slab Lattices
Kalimullah, K. S. Ram, G. Srikantiah
Nuclear Science and Engineering | Volume 49 | Number 3 | November 1972 | Pages 376-384
Technical Note | doi.org/10.13182/NSE72-A22550
The Treatment of Boundary Value Problems in Optically Thick Media by Means of Lie Series
T. Auerbach, W. Hälg, J. Mennig
Nuclear Science and Engineering | Volume 49 | Number 3 | November 1972 | Pages 384-387
Technical Note | doi.org/10.13182/NSE72-A22551
Calculations of Cadmium Cutoff Energies
Antanasije Koci
Nuclear Science and Engineering | Volume 49 | Number 3 | November 1972 | Pages 387-389
Technical Note | doi.org/10.13182/NSE72-A22552
Note on the Fast Neutron Cross Sections of Palladium
A. B. Smith, P. Lambropoulos, P. Guenther, J. Whalen
Nuclear Science and Engineering | Volume 49 | Number 3 | November 1972 | Pages 389-392
Technical Note | doi.org/10.13182/NSE72-A22553
Total Neutron Cross Section of Mylar at Low Energies
C. Castro Madero, F. Kropff, A. Oliva, J. M. Neill
Nuclear Science and Engineering | Volume 49 | Number 3 | November 1972 | Pages 392-393
Technical Note | doi.org/10.13182/NSE72-A22554
Specification and Testing of Nuclear Data Required for Monte Carlo Transport Calculations
E. D. Cashwell, E. F. Plechaty
Nuclear Science and Engineering | Volume 49 | Number 3 | November 1972 | Pages 394-395
Technical Note | doi.org/10.13182/NSE72-A22555
The Validity of Using Only Primary Protons in Van Allen Belt and Solar-Flare Proton Shielding Studies
R. T. Santoro, R. G. Alsmiller, Jr., J. Barish
Nuclear Science and Engineering | Volume 49 | Number 3 | November 1972 | Pages 395-398
Technical Note | doi.org/10.13182/NSE72-A22556
Laminar- and Slug-Flow Heat Transfer Characteristics of Fuel Rods Adjacent to Fuel Subassembly Walls
Chia-Jung Hsu
Nuclear Science and Engineering | Volume 49 | Number 3 | November 1972 | Pages 398-404
Technical Note | doi.org/10.13182/NSE72-A22557
Radiation Transport in a Halfspace with a Source External to the Medium
G. C. Pomraning
Nuclear Science and Engineering | Volume 49 | Number 4 | December 1972 | Pages 409-417
Technical Paper | doi.org/10.13182/NSE72-A22561
Time-Dependent Leakage Neutron Spectrum Studies of Some Small Hydrogenous Moderators
Kingsley F Graham, John M. Carpenter
Nuclear Science and Engineering | Volume 49 | Number 4 | December 1972 | Pages 418-437
Technical Paper | doi.org/10.13182/NSE72-A22562
An Investigation of Non-Exponential Decay of Neutron Distributions in Graphite
Harold F. McFarlane
Nuclear Science and Engineering | Volume 49 | Number 4 | December 1972 | Pages 438-449
Technical Paper | doi.org/10.13182/NSE72-A22563
The Probability Table Method for Treating Unresolved Neutron Resonances in Monte Carlo Calculations
Leo B. Levitt
Nuclear Science and Engineering | Volume 49 | Number 4 | December 1972 | Pages 450-457
Technical Paper | doi.org/10.13182/NSE72-3
A New Method for Analysis of Pulsed Fast Neutron Experiments
Shin-ichi Ito
Nuclear Science and Engineering | Volume 49 | Number 4 | December 1972 | Pages 458-467
Technical Paper | doi.org/10.13182/NSE72-A22565
Reactivity Worths of Boron, Tantalum, and Europium in a Fast Reactor Spectrum
R. J. Tuttle, T. H. Springer
Nuclear Science and Engineering | Volume 49 | Number 4 | December 1972 | Pages 468-481
Technical Paper | doi.org/10.13182/NSE72-A22566
Reactor Depletion Analyzed as a Space-Time Problem
William J. Westlake, Jr., A. F. Henry
Nuclear Science and Engineering | Volume 49 | Number 4 | December 1972 | Pages 482-488
Technical Paper | doi.org/10.13182/NSE72-A22567
Criticality of Graphite- and Polyethylene-Reflected Uranium (93.2%)-Metal Cylinders and Annuli
J. T. Mihalczo
Nuclear Science and Engineering | Volume 49 | Number 4 | December 1972 | Pages 489-504
Technical Paper | doi.org/10.13182/NSE72-A22568
A Fitting Function for Energy Dissipation Curves of Fast Electrons
Tatsuo Tabata, Rinsuke Ito, Shigeru Okabe
Nuclear Science and Engineering | Volume 49 | Number 4 | December 1972 | Pages 505-506
Technical Notes | doi.org/10.13182/NSE72-A22569
Temperature Dependence of Uranium Carbide Fission-Gas Swelling: An Analytical Evaluation
Alan J. Markworth
Nuclear Science and Engineering | Volume 49 | Number 4 | December 1972 | Pages 506-507
Technical Notes | doi.org/10.13182/NSE72-A22570
Exact Collision Probabilities for Spherical Shells in a Homogeneous Medium
Tomas Lefvert
Nuclear Science and Engineering | Volume 49 | Number 4 | December 1972 | Pages 507-509
Technical Notes | doi.org/10.13182/NSE72-A22571
The Transverse Diffusion Coefficient in a Square Lattice
Nuclear Science and Engineering | Volume 49 | Number 4 | December 1972 | Pages 509-515
Technical Notes | doi.org/10.13182/NSE72-A22572
Optimization of Control Rod Programming and Loading Pattern in Multiregion Nuclear Reactor by the Method of Approximation Programming
Hiroshi Motoda
Nuclear Science and Engineering | Volume 49 | Number 4 | December 1972 | Pages 515-524
Technical Notes | doi.org/10.13182/NSE72-A22573