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Deposition of Particles in Turbulent Flow on Channel or Pipe Walls
S. K. Beal
Nuclear Science and Engineering | Volume 40 | Number 1 | April 1970 | Pages 1-11
Technical Paper | doi.org/10.13182/NSE70-A18874
The Thermal-Neutron-Absorption Cross Sections of 6Li and 10B
J. W. Meadows, J. F. Whalen
Nuclear Science and Engineering | Volume 40 | Number 1 | April 1970 | Pages 12-16
Technical Paper | doi.org/10.13182/NSE70-A18875
Approximate Dispersion Relations and the Total Coherent Inelastic Neutron Scattering Cross Section for Graphite
Robert Conn
Nuclear Science and Engineering | Volume 40 | Number 1 | April 1970 | Pages 17-24
Technical Paper | doi.org/10.13182/NSE70-A18876
The Construction of Neutron Cross Sections in the Unresolved Resonance Region
Yukio Ishiguro, Satoru Katsuragi, Masayuki Nakagawa, Hideki Takano
Nuclear Science and Engineering | Volume 40 | Number 1 | April 1970 | Pages 25-37
Technical Paper | doi.org/10.13182/NSE70-A18877
The Linear Vector Space Theory of Unfolding
N. Karayianis, C. A. Morrison, D. E. Wortman
Nuclear Science and Engineering | Volume 40 | Number 1 | April 1970 | Pages 38-50
Technical Paper | doi.org/10.13182/NSE70-A18878
Evaluation of Neutron Spectral Effects in Systems with Thermal Resonance Absorbers by Applying a Correlation Method to Measured Spectral Indexes
A. Gibello, F. V. Orestano, F. Pistella, E. Santandrea
Nuclear Science and Engineering | Volume 40 | Number 1 | April 1970 | Pages 51-72
Technical Paper | doi.org/10.13182/NSE70-A18879
General Multigroup and Spectral Synthesis Equations
Weston M. Stacey, Jr.
Nuclear Science and Engineering | Volume 40 | Number 1 | April 1970 | Pages 73-90
Technical Paper | doi.org/10.13182/NSE70-A18880
Numerical Solution of the Time- and Space-Dependent Multigroup Neutron Diffusion Equations
W. R. Rhyne, A. C. Lapsley
Nuclear Science and Engineering | Volume 40 | Number 1 | April 1970 | Pages 91-100
Technical Paper | doi.org/10.13182/NSE70-A18881
A Study of Physics Parameters in Several H2O-Moderated Lattices of Slightly Enriched and Natural Uranium
J. Hardy, Jr., D. Klein, J. J. Volpe
Nuclear Science and Engineering | Volume 40 | Number 1 | April 1970 | Pages 101-115
Technical Paper | doi.org/10.13182/NSE70-A18882
A Comparison of Thermal-Neutron-Activation Measurements and Monte Carlo Calculations in Light-Water-Moderated Uranium Cells
J. J. Volpe, J. Hardy, Jr., D. Klein
Nuclear Science and Engineering | Volume 40 | Number 1 | April 1970 | Pages 116-127
Technical Paper | doi.org/10.13182/NSE70-A18883
Buildup Factors in Water for Gamma Rays of 1 MeV and Lower Energy
E. E. Morris, A. B. Chilton
Nuclear Science and Engineering | Volume 40 | Number 1 | April 1970 | Pages 128-129
Technical Note | doi.org/10.13182/NSE70-A18884
Reduction of the Residual Photon Dose Rate Around High-Energy Proton Accelerators
T. W. Armstrong, J. Barish
Nuclear Science and Engineering | Volume 40 | Number 1 | April 1970 | Pages 129-132
Technical Note | doi.org/10.13182/NSE70-A18885
Null-Reactivity Measurements of Capture/Fission Ratio in 235U and 239Pu
C. E. Till, J. M. Gasidlo, E. F. Groh, L. G. LeSage, W. R. Robinson, G. S. Stanford
Nuclear Science and Engineering | Volume 40 | Number 1 | April 1970 | Pages 132-136
Technical Note | doi.org/10.13182/NSE70-A18886
Cross Section for the Delayed-Neutron Yield from the 17O(n,p)17N Reaction at 14.1 MeV
H. O. Menlove, R. H. Augustson, C. N. Henry
Nuclear Science and Engineering | Volume 40 | Number 1 | April 1970 | Pages 136-138
Technical Note | doi.org/10.13182/NSE70-A18887
Heterogeneity Effects on Neutron Self-Shielding Factors for Fast Reactors
G. Bitelli, M. Salvatores, G. Cecchini
Nuclear Science and Engineering | Volume 40 | Number 1 | April 1970 | Pages 138-140
Technical Note | doi.org/10.13182/NSE70-A18888
Pulse Characteristics for Ramp Reactivity Insertion and Energy-Shutdown Reactor Excursions
R. F. Redmond
Nuclear Science and Engineering | Volume 40 | Number 1 | April 1970 | Pages 141-144
Technical Note | doi.org/10.13182/NSE70-A18890
On the Effect of Delayed Neutrons in Reactor Excursions with Ramp Reactivity Insertion
David L. Hetrick, José Canosa
Nuclear Science and Engineering | Volume 40 | Number 1 | April 1970 | Page 141
Technical Note | doi.org/10.13182/NSE70-A18889
Reactivity Changes Due to the Random Vibration of Control Rods and Fuel Elements
M. M. R. Williams
Nuclear Science and Engineering | Volume 40 | Number 1 | April 1970 | Pages 144-150
Technical Note | doi.org/10.13182/NSE70-A18891
Qualitative Evaluation of Fast Reactor Melt-Down Accidents
Masaoki Komata
Nuclear Science and Engineering | Volume 40 | Number 1 | April 1970 | Pages 150-152
Technical Note | doi.org/10.13182/NSE70-A18892
The Statistical Uncertainty in Doppler Coefficient Calculations for Fast Reactors
C. R. Adkins, M. W. Dyos
Nuclear Science and Engineering | Volume 40 | Number 2 | May 1970 | Pages 159-172
Technical Paper | doi.org/10.13182/NSE70-A19680
Measurements and Detailed Model Analysis of Space-Correlated Reactor Fluctuations
D. R. Harris, M. Natelson, J. A. Galey, E. Schmidt
Nuclear Science and Engineering | Volume 40 | Number 2 | May 1970 | Pages 173-198
Technical Paper | doi.org/10.13182/NSE70-A19681
Estimation of the Dynamic Reactivity Using Digital Kalman Filtering
Joseph C. Venerus, Thomas E. Bullock
Nuclear Science and Engineering | Volume 40 | Number 2 | May 1970 | Pages 199-205
Technical Paper | doi.org/10.13182/NSE70-A19682
Weighted-Residual Methods in Space-Dependent Reactor Dynamics
E. L. Fuller, D. A. Meneley, D. L. Hetrick
Nuclear Science and Engineering | Volume 40 | Number 2 | May 1970 | Pages 206-223
Technical Paper | doi.org/10.13182/NSE70-A19683
The Integral Transform Method for Neutron Transport Problems
H. Hembd
Nuclear Science and Engineering | Volume 40 | Number 2 | May 1970 | Pages 224-238
Technical Paper | doi.org/10.13182/NSE70-A19684
Point Source Green's Functions for Neutral Particle Transport
James F. Meyer, Alan M. Jacobs
Nuclear Science and Engineering | Volume 40 | Number 2 | May 1970 | Pages 239-245
Technical Paper | doi.org/10.13182/NSE70-A19685
Study of the Use of Pulsed-Neutron Experiments on Multiplying Lattices for the Adjustment of Criticality Codes
V. Deniz
Nuclear Science and Engineering | Volume 40 | Number 2 | May 1970 | Pages 246-253
Technical Paper | doi.org/10.13182/NSE70-A19686
Calculation of the Neutron Spectra from Proton-Nucleus Nonelastic Collisions in the Energy Range 15 to 18 MeV and Comparison with Experiment
R. G. Alsmiller, Jr., O. W. Hermann
Nuclear Science and Engineering | Volume 40 | Number 2 | May 1970 | Pages 254-261
Technical Paper | doi.org/10.13182/NSE70-A19687
Predictions for Neutron Transport in Air, Based on Integral Measurements in Nitrogen and Oxygen at 14 MeV
L. F. Hansen, J. D. Anderson, E. Goldberg, J. Kammerdiener, E. Plechaty, C. Wong
Nuclear Science and Engineering | Volume 40 | Number 2 | May 1970 | Pages 262-282
Technical Paper | doi.org/10.13182/NSE70-A19688
The 160(n,xγ) Reaction for 67 ≤ En ≤ 11 MeV
J. K. Dickens, F. G. Perey
Nuclear Science and Engineering | Volume 40 | Number 2 | May 1970 | Pages 283-293
Technical Paper | doi.org/10.13182/NSE70-A19689
Gamma-Ray-Production Cross Sections for Fast Neutron Interactions with Several Elements
Darrell M. Drake, John C. Hopkins, C. S. Young, H. Condé
Nuclear Science and Engineering | Volume 40 | Number 2 | May 1970 | Pages 294-305
Technical Paper | doi.org/10.13182/NSE70-A19690
Measurements of the Neutron Fission and Absorption Cross Sections of 239Pu Over the Energy Region 0.02 eV to 30 keV
R. Gwin, L. W. Weston, G. de Saussure, R. W. Ingle, J. H. Todd, F. E. Gillespie, R. W. Hockenbury, R. C. Block
Nuclear Science and Engineering | Volume 40 | Number 2 | May 1970 | Pages 306-316
Technical Paper | doi.org/10.13182/NSE70-A19691
Effects of Cladding Thickness and Thermal Conductivity on Heat Transfer to Liquid Metals Flowing In-Line Through Bundles of Closely Spaced Reactor Fuel Rods
O. E. Dwyer, H. C. Berry
Nuclear Science and Engineering | Volume 40 | Number 2 | May 1970 | Pages 317-330
Technical Paper | doi.org/10.13182/NSE70-A19692
Threshold Reaction Excitation Functions Intercalibrated in a Pure Fission Spectrum
A.M. Bresesti, M. Bresesti, A. Rota, R. A. Rydin, L. Lesca
Nuclear Science and Engineering | Volume 40 | Number 2 | May 1970 | Pages 331-338
Technical Note | doi.org/10.13182/NSE70-A19693
A Multigroup Two-Point Kinetic Model for the Time-Dependent Analysis of Two-Zone Fast Neutron Systems
P. d'Oultremont, J. C. Young
Nuclear Science and Engineering | Volume 40 | Number 2 | May 1970 | Pages 338-342
Technical Note | doi.org/10.13182/NSE70-A19694
Multilevel Parameters for the 239Pu Fission Cross Section from 40 to 100 eV
P. Lambropoulos
Nuclear Science and Engineering | Volume 40 | Number 2 | May 1970 | Pages 342-346
Technical Note | doi.org/10.13182/NSE70-A19695
The 14N(n,xγ) Reaction for 8.5 ≤ En ≤ 11 MeV
Nuclear Science and Engineering | Volume 40 | Number 2 | May 1970 | Pages 346-348
Technical Note | doi.org/10.13182/NSE70-A19696
The Energy Distribution of Photoneutrons Produced by 150-MeV Electrons in Thick Beryllium and Tantalum Targets
R. G. Alsmiller, Jr., T. A. Gabriel, M. P. Guthrie
Nuclear Science and Engineering | Volume 40 | Number 3 | June 1970 | Pages 365-374
Technical Paper | doi.org/10.13182/NSE70-A20187
A Measurement of the Fission Cross Sections of 239Pu and 233U Relative to 235U
E. Pfletschinger, F. Käppeler
Nuclear Science and Engineering | Volume 40 | Number 3 | June 1970 | Pages 375-382
Technical Paper | doi.org/10.13182/NSE70-A20188
Measurement of the Ratios of Capture and Fission Neutron Cross Sections of 235U, 238U, and 239Pu at 130 to 1400 keV
W. P. Poenitz
Nuclear Science and Engineering | Volume 40 | Number 3 | June 1970 | Pages 383-388
Technical Paper | doi.org/10.13182/NSE70-A20189
Total Neutron Cross Section of 242Pu
T. E. Young, S. D. Reeder
Nuclear Science and Engineering | Volume 40 | Number 3 | June 1970 | Pages 389-395
Technical Paper | doi.org/10.13182/NSE70-A20190
Calculated 56Fe Neutron Elastic and Inelastic Scattering and Gamma-Ray-Production Cross Sections from 1.0 to 7.6 MeV
W. E. Kinney, F. G. Perey
Nuclear Science and Engineering | Volume 40 | Number 3 | June 1970 | Pages 396-406
Technical Paper | doi.org/10.13182/NSE70-A20191
Critical Parameters of a Uranium Solution Slab-Cylinder System
Grover Tuck, Harold E. Clark
Nuclear Science and Engineering | Volume 40 | Number 3 | June 1970 | Pages 407-413
Technical Paper | doi.org/10.13182/NSE70-A20192
Analysis of Central Reactivity Worths in Fast Critical Assemblies
R. A. Karam, K. D. Dance, T. Nakamura, J. E. Marshall
Nuclear Science and Engineering | Volume 40 | Number 3 | June 1970 | Pages 414-423
Technical Paper | doi.org/10.13182/NSE70-A20193
An Approximate Solution to the Asymptotic Slowing Down Equations of Fast Neutrons
M. Segev
Nuclear Science and Engineering | Volume 40 | Number 3 | June 1970 | Pages 424-437
Technical Paper | doi.org/10.13182/NSE70-A20194
Some Monte Carlo Techniques for the Calculation of Doppler Coefficients
L. B. Miller, G. H. Miley
Nuclear Science and Engineering | Volume 40 | Number 3 | June 1970 | Pages 438-448
Technical Paper | doi.org/10.13182/NSE70-A20195
Verification of Space-Time Reactor-Kinetics Analysis by Experiments
H. H. Hassan, G. H. Miley
Nuclear Science and Engineering | Volume 40 | Number 3 | June 1970 | Pages 449-459
Technical Paper | doi.org/10.13182/NSE70-A20196
Space- and Time-Dependent Neutron Slowing Down
David J. Diamond, Sidney Yip
Nuclear Science and Engineering | Volume 40 | Number 3 | June 1970 | Pages 460-471
Technical Paper | doi.org/10.13182/NSE70-A20197
Effect of Neutron Anisotropy on the Depletion of a Cylindrical Burnable Poison Pin
M. G. Zaalouk, J. O. Berg
Nuclear Science and Engineering | Volume 40 | Number 3 | June 1970 | Pages 472-477
Technical Paper | doi.org/10.13182/NSE70-A20198
Use of Gauss-Laguerre Numerical Integration for Point Kernel Shielding Calculations
P. C. Cochrane, D. W. Mesh
Nuclear Science and Engineering | Volume 40 | Number 3 | June 1970 | Pages 478-483
Technical Note | doi.org/10.13182/NSE70-A20199
Calculation of the Energy Deposited in Thick Targets by High-Energy (1 GeV) Electron-Photon Cascades and Comparison with Experiment—II
R. G. Alsmiller, Jr., H. S. Moran
Nuclear Science and Engineering | Volume 40 | Number 3 | June 1970 | Pages 483-485
Technical Note | doi.org/10.13182/NSE70-A20200
Prompt Gamma Rays from Thermal Neutron Fission of Uranium-235
R. W. Peelle, F. C. Maienschein
Nuclear Science and Engineering | Volume 40 | Number 3 | June 1970 | Pages 485-486
Technical Note | doi.org/10.13182/NSE70-A20201
Photon Cross Sections of Uranium and Plutonium
H. F. Atwater
Nuclear Science and Engineering | Volume 40 | Number 3 | June 1970 | Pages 487-488
Technical Note | doi.org/10.13182/NSE70-A20202
A Numerical Calculation of the Time-Dependent Neutron Spectra in a Pulsed Homogeneous Multiplying System
Pablo Rodriguez, Dong H. Nguyen
Nuclear Science and Engineering | Volume 40 | Number 3 | June 1970 | Pages 488-491
Technical Note | doi.org/10.13182/NSE70-A20203
Several Particular Solutions of the One-Speed Transport Equation
M. N. Özişik, C. E. Siewert
Nuclear Science and Engineering | Volume 40 | Number 3 | June 1970 | Pages 491-494
Technical Note | doi.org/10.13182/NSE70-A20204
Prompt-Jump Correction of Inverse Kinetics Rod-Drop Measurements
Günter Kussmaul
Nuclear Science and Engineering | Volume 40 | Number 3 | June 1970 | Pages 494-498
Technical Note | doi.org/10.13182/NSE70-A20205
Approximate Calculation of Prompt-Critical Excursions
Rubin Goldstein, Louis M. Shotkin
Nuclear Science and Engineering | Volume 40 | Number 3 | June 1970 | Pages 498-500
Technical Note | doi.org/10.13182/NSE70-A20206
