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Two-Group Critical Problems for Slabs and Spheres in Neutron-Transport Theory
J. T. Kriese, C. E. Siewert, Y. Yener
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 3-9
Technical Paper | doi.org/10.13182/NSE73-A22582
Neutron Transport for a Slab with a Degenerate Scattering Kernel
H. A. Larson, N. J. McCormick
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 10-19
Technical Paper | doi.org/10.13182/NSE73-A22583
Improved Moment Method Calculations of Gamma-Ray Transport: Application to Point Isotropic Sources in Water
L. V. Spencer, G. L. Simmons
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 20-31
Technical Paper | doi.org/10.13182/NSE73-A22584
Moments Method Calculation of Buildup Factors for Point Isotropic Monoenergetic Gamma-Ray Sources at Depths Greater than 20 Mean-Free-Paths
E. E. Morris
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 32-37
Technical Paper | doi.org/10.13182/NSE73-A22585
A Pulsed Neutron Experiment with Beryllium by the Use of a Gamma-Ray Flash from an Electron Linear Accelerator
Otohiko Aizawa, Hiroyuki Kadotani, Keiji Kanda, Yoshiaki Fujita
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 38-45
Technical Paper | doi.org/10.13182/NSE73-A22586
On the Use of Maximum Principle in Optimal Xenon Shutdown Problems
Seppo Salo
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 46-52
Technical Paper | doi.org/10.13182/NSE73-A22587
Analysis of the Coolant Behavior Following Fuel Failure and Molten Fuel-Sodium Interaction in a Fast Nuclear Reactor
A. W. Cronenberg, H. K. Fauske, D. T. Eggen
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 53-62
Technical Paper | doi.org/10.13182/NSE73-A22588
Sensitivity Analysis of Ideal Centrifuge Cascade for Producing Slightly Enriched Uranium
Toshio Kawai, Kotaro Inoue, Hiroshi Motoda, Tomofumi Kobayashi, Takashi Kiguchi
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 63-72
Technical Paper | doi.org/10.13182/NSE73-A22589
Monte Carlo Confidence Limits for Iterated-Source Calculations
D. B. MacMillan
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 73-75
Technical Note | doi.org/10.13182/NSE73-A22590
Studies in Spectral Neutron Flux Synthesis
Harold Greenspan
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 75-78
Technical Note | doi.org/10.13182/NSE73-A22591
The Effective Cross Section for the 16O(d, n)17 F Reaction for Fission Neutrons Moderated by Heavy Water
H. S. Pruys, B. D. Ganapol
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 79-80
Technical Note | doi.org/10.13182/NSE73-A22592
Revised Delayed-Neutron Yield Data
A. E. Evans, M. M. Thorpe, M. S. Krick
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 80-82
Technical Note | doi.org/10.13182/NSE73-A22593
Merit Index for Gas-Cooled Reactor Heat Transfer
G. Melese-d’Hospital
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 83-85
Technical Note | doi.org/10.13182/NSE73-A22594
Thermal Characterization of Restructured Fuel
Aaron J. Friedland
Nuclear Science and Engineering | Volume 50 | Number 1 | January 1973 | Pages 85-87
Technical Note | doi.org/10.13182/NSE73-A22595
Mixed Sorption Models and Isotherms of the Cesium-Rubidium-Graphite System at High Temperatures
M. J. Haire, L. R. Zumwalt
Nuclear Science and Engineering | Volume 50 | Number 2 | February 1973 | Pages 91-97
Technical Paper | doi.org/10.13182/NSE73-A23232
The Neutron-Induced Gamma-Ray Reactions in Sodium-23 in the Energy Range 4.85 ≤ En ≤ 7.5 MeV
J. K. Dickens
Nuclear Science and Engineering | Volume 50 | Number 2 | February 1973 | Pages 98-107
Technical Paper | doi.org/10.13182/NSE73-A23233
The Energy Spectrum of Prompt Neutrons from the Fission of Uranium-235 by 0.40-MeV Neutrons
M. M. Islam, H. -H. Knitter
Nuclear Science and Engineering | Volume 50 | Number 2 | February 1973 | Pages 108-114
Technical Paper | doi.org/10.13182/NSE73-A23234
Critical Experiments with Homogeneous Mixtures of Plutonium and Uranium Oxides Containing 8,15, and 30 wt% Plutonium
S. R. Bierman, E. D. Clayton, L. E. Hansen
Nuclear Science and Engineering | Volume 50 | Number 2 | February 1973 | Pages 115-126
Technical Paper | doi.org/10.13182/NSE73-2
Criticality of Plutonium Nitrate Solutions Containing Borated Raschig Rings
R. C. Lloyd, S. R. Bierman, E. D. Clayton
Nuclear Science and Engineering | Volume 50 | Number 2 | February 1973 | Pages 127-134
Technical Paper | doi.org/10.13182/NSE73-A23236
Improved Integral Transport Theory by Means of Space Polynomial Approximations
J. Ligou
Nuclear Science and Engineering | Volume 50 | Number 2 | February 1973 | Pages 135-146
Technical Paper | doi.org/10.13182/NSE73-A23237
Higher Flux Mode Effects in Xenon Spatial Oscillations
R. A. Rydin
Nuclear Science and Engineering | Volume 50 | Number 2 | February 1973 | Pages 147-152
Technical Paper | doi.org/10.13182/NSE73-A23238
Optimal Fuel Enrichment Distribution in Fast Reactors
P. Goldschmidt
Nuclear Science and Engineering | Volume 50 | Number 2 | February 1973 | Pages 153-163
Technical Paper | doi.org/10.13182/NSE73-A23239
An Integral Formulation of the Neutron Scattering Moments for Monatomic Gases
Nicholas H. Kuehn III, Raymond L. Murray
Nuclear Science and Engineering | Volume 50 | Number 2 | February 1973 | Pages 164-169
Technical Note | doi.org/10.13182/NSE73-A23240
Neutron Multiplicity Distributions in the Spontaneous Fission of 244Cm, 248Cm, and 252Cf
R. W. Stoughton, J. Halperin, C. E. Bemis, H. W. Schmitt
Nuclear Science and Engineering | Volume 50 | Number 2 | February 1973 | Pages 169-171
Technical Note | doi.org/10.13182/NSE73-A23241
Average Neutron Cross Sections in the Unresolved Resonance Range
Mendel Beer
Nuclear Science and Engineering | Volume 50 | Number 2 | February 1973 | Pages 171-173
Technical Note | doi.org/10.13182/NSE73-A23242
Effect of Delayed-Neutron Mode on the Determination of the Prompt-Neutron Decay Constant in Pulsed-Neutron Measurements
Yoshihiko Kaneko, Shuzi Ohkubo, Fujiyoshi Akino
Nuclear Science and Engineering | Volume 50 | Number 2 | February 1973 | Pages 173-176
Technical Note | doi.org/10.13182/NSE73-A23243
Correlating the Ratio of the Peak-to-Average Power in a Reactor with Quadrant Power Distributions
M. M. Levine
Nuclear Science and Engineering | Volume 50 | Number 2 | February 1973 | Pages 176-179
Technical Note | doi.org/10.13182/NSE73-A23244
Numerical Methods of High Order Accuracy for One-Dimensional Diffusion Equation
J. P. Hennart
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 185-199
Technical Paper | doi.org/10.13182/NSE73-A28971
The Neutron Diffusion Coefficient as a Second-Order Tensor—Theory and Calculations
V. C. Boffi, T. Trombetti
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 200-207
Technical Paper | doi.org/10.13182/NSE73-A28972
Delayed Neutron Data for Fast Reactor Analysis
J. E. Cahalan, K. O. Ott
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 208-215
Technical Paper | doi.org/10.13182/NSE73-A28973
On the Applicability of Sjöstrand’s Area Method for Reactivity Measurement by the Pulsed-Neutron Technique
Jan B. Dragt
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 216-219
Technical Paper | doi.org/10.13182/NSE73-A28974
A Bilinear Formulation for Spatial Cross-Section Averaging
Masaoki Komata, Richard B. Nicholson, Earl M. Page
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 220-228
Technical Paper | doi.org/10.13182/NSE73-A28975
A Study of Several Methods for Analysis of Critical Assembly Heterogeneity
R. G. Palmer, J. P. Plummer, R. B. Nicholson
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 229-242
Technical Paper | doi.org/10.13182/NSE73-A28976
The Total Neutron Cross Sections of Uranium-238 from 0.8 to 30 MeV
S. H. Hayes, P. Stoler, J. M. Clement, C. A. Goulding
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 243-247
Technical Paper | doi.org/10.13182/NSE73-A28977
Measurement of Bremsstrahlung Spectra Produced in Iron and Tungsten Targets by 15-MeV Electrons with Activation Detectors
Hideo Hirayama, Takashi Nakamura
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 248-256
Technical Paper | doi.org/10.13182/NSE73-A28978
The Californium-252 Fission Neutron Spectrum from 0.5 to 13 MeV
L. Green, J. A. Mitchell, N. M. Steen
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 257-272
Technical Paper | doi.org/10.13182/NSE73-A28979
A Study of Fission-Fragment-Induced Nucleation of Bubbles in Superheated Water
L. W. Deitrich, T. J. Connolly
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 273-282
Technical Paper | doi.org/10.13182/NSE73-A28980
Thermal Contact Conductance in Reactor Fuel Elements
Gary Jacobs, Neil Todreas
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 283-290
Technical Note | doi.org/10.13182/NSE73-A28981
Errors in Perturbation Calculations
C. W. J. McCallien
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 290-293
Technical Note | doi.org/10.13182/NSE73-A28982
Second-Order Boltzmann Equation from Invariant Imbedding Theory
Zbigniew Weiss
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 294-297
Technical Note | doi.org/10.13182/NSE73-A28983
Computational Experimentation on the Finite Element Method in Bare Slab Criticality Calculations
Juhani Pitkäranta, Pekka Silvennoinen
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 297-300
Technical Note | doi.org/10.13182/NSE73-A28984
Variational Estimates of the Detector Response Change in a Fixed Source System Due to Cross-Section Perturbations
T. J. Hoffman
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 300-302
Technical Note | doi.org/10.13182/NSE73-A28985
In-Core Neutron Flux Distribution Measurement by a Circulating Fluid Activation Method
Masaaki Fujii
Nuclear Science and Engineering | Volume 50 | Number 3 | March 1973 | Pages 302-306
Technical Note | doi.org/10.13182/NSE73-A28986
Neutron-Induced Gamma-Ray Production in Iron for the Energy Range 0.8 ≤ En ≤ 20 MeV
J. K. Dickens, G. L. Morgan, F. G. Perey
Nuclear Science and Engineering | Volume 50 | Number 4 | April 1973 | Pages 311-336
Technical Paper | doi.org/10.13182/NSE73-A26567
Neutron Thermalization in Various H2O-D2O Mixtures in the Temperature Range 253 to 4°K
G. S. Gangwani, S. P. Tewari, L. S. Kothari
Nuclear Science and Engineering | Volume 50 | Number 4 | April 1973 | Pages 337-344
Technical Paper | doi.org/10.13182/NSE73-A26568
Adjustment of Multigroup Neutron Cross Sections by a Correlation Method
M. Salvatores
Nuclear Science and Engineering | Volume 50 | Number 4 | April 1973 | Pages 345-353
Technical Paper | doi.org/10.13182/NSE73-A26569
A Many-Resonance Approximation for the Neutron Energy Spectrum
M. Segev
Nuclear Science and Engineering | Volume 50 | Number 4 | April 1973 | Pages 354-363
Technical Paper | doi.org/10.13182/NSE73-A26570
Thermal-Neutron Capture Cross Sections and Capture Resonance Integrals of Americium-241
R. M. Harbour, K. W. MacMurdo, F. J. McCrosson
Nuclear Science and Engineering | Volume 50 | Number 4 | April 1973 | Pages 364-369
Technical Paper | doi.org/10.13182/NSE73-A26571
Stability of Nuclear Reactors with Changes in Eigenvalue
Dong H. Nguyen
Nuclear Science and Engineering | Volume 50 | Number 4 | April 1973 | Pages 370-381
Technical Paper | doi.org/10.13182/NSE73-A26572
Two-Phase Mixing for Annular Flow in Simulated Rod Bundle Geometries
Kuldip Singh, C. C. St. Pierre
Nuclear Science and Engineering | Volume 50 | Number 4 | April 1973 | Pages 382-387
Technical Note | doi.org/10.13182/NSE73-A26573
Extrapolated Endpoint for the Uniform Source Half-Space Problem
W. P. Petrick, C. T. McDaniel, A. Leonard
Nuclear Science and Engineering | Volume 50 | Number 4 | April 1973 | Pages 388-390
Technical Note | doi.org/10.13182/NSE73-A26574
Interpolation of Tabular Secondary Neutron and Photon Energy Distributions
Richard J. Doyas, Sterrett T. Perkins
Nuclear Science and Engineering | Volume 50 | Number 4 | April 1973 | Pages 390-392
Technical Note | doi.org/10.13182/NSE73-A26575
The (n, γn’) Reaction in Calculations of Fast Reactor Neutron Spectra
M. P. Fricke, J. M. Neill
Nuclear Science and Engineering | Volume 50 | Number 4 | April 1973 | Pages 392-397
Technical Note | doi.org/10.13182/NSE73-A26576
Effect of the 238U(n, γn’) Reaction in Fast-Neutron Spectrum Critical Assemblies
Harry H. Hummel, Weston M. Stacey, Jr.
Nuclear Science and Engineering | Volume 50 | Number 4 | April 1973 | Pages 397-398
Technical Note | doi.org/10.13182/NSE73-A26577
Exact Time-Dependent Second Spatial Moment of the One-Speed Neutron Transport Model
C. S. Barnett
Nuclear Science and Engineering | Volume 50 | Number 4 | April 1973 | Pages 398-401
Technical Note | doi.org/10.13182/NSE73-A26578