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A Generalization of the Finite Difference Approximation Method with an Application to Space-Time Nuclear Reactor Kinetics
Raymond E. Alcouffe, Robert W. Albrecht
Nuclear Science and Engineering | Volume 39 | Number 1 | January 1970 | Pages 1-13
Technical Paper | doi.org/10.13182/NSE70-A21166
Improvements in Fast Reactor Space-Energy Synthesis
R. J. Neuhold, K. O. Ott
Nuclear Science and Engineering | Volume 39 | Number 1 | January 1970 | Pages 14-24
Technical Paper | doi.org/10.13182/NSE70-A21167
Doppler Broadening in a Medium with Both Temperature and Boundary Motion
S. T. Perkins
Nuclear Science and Engineering | Volume 39 | Number 1 | January 1970 | Pages 25-31
Technical Paper | doi.org/10.13182/NSE70-A21168
Doppler Effect Studies Using Multilevel Formalism
R. N. Hwang
Nuclear Science and Engineering | Volume 39 | Number 1 | January 1970 | Pages 32-49
Technical Paper | doi.org/10.13182/NSE70-A21169
Determination of Fission Density in 235U and Implications from Its Mass Distribution
Petru Popa, Marcel De Coster, Pieter H. M. Van Assche
Nuclear Science and Engineering | Volume 39 | Number 1 | January 1970 | Pages 50-55
Technical Paper | doi.org/10.13182/NSE70-A21170
The Influence of a Reentrant Hole on Measurements of Fast and Thermal Neutron Spectra
Frank McGirt, Martin Becker
Nuclear Science and Engineering | Volume 39 | Number 1 | January 1970 | Pages 56-66
Technical Paper | doi.org/10.13182/NSE70-A21171
Fast Neutron Cross Sections of Hafnium, Gadolinium, and Samarium
G. L. Sherwood, A. B. Smith, J. F. Whalen
Nuclear Science and Engineering | Volume 39 | Number 1 | January 1970 | Pages 67-80
Technical Paper | doi.org/10.13182/NSE70-A21172
Gamma-Ray Spectra of the Products of Thermal-Neutron Fission of 235U at Selected Times after Fission
L. R. Bunney, D. Sam
Nuclear Science and Engineering | Volume 39 | Number 1 | January 1970 | Pages 81-91
Technical Paper | doi.org/10.13182/NSE70-A21173
Theoretical Dose Transmission and Reflection Probabilities for 0.2-10.0 MeV Photons Obliquely Incident on Finite Concrete Barriers
W. O. Doggett, Fred A. Bryan, Jr.
Nuclear Science and Engineering | Volume 39 | Number 1 | January 1970 | Pages 92-104
Technical Paper | doi.org/10.13182/NSE70-1
Construction of Lyapunov Functions for Nonlinear Reactor Stability Studies
M. A. Pai, V. R. Sastry, M. Ananda Mohan
Nuclear Science and Engineering | Volume 39 | Number 1 | January 1970 | Pages 105-107
Technical Note | doi.org/10.13182/NSE70-A21175
Comparison of Methods for Determining Moderator Level Reactivity Coefficients
S. E. Wennemo-Hanssen
Nuclear Science and Engineering | Volume 39 | Number 1 | January 1970 | Pages 107-109
Technical Note | doi.org/10.13182/NSE70-A21176
Control Rod Programming Optimization Using Dynamic Programming
William B. Terney, Henri Fenech
Nuclear Science and Engineering | Volume 39 | Number 1 | January 1970 | Pages 109-114
Technical Note | doi.org/10.13182/NSE70-A21177
A Theory of Control-Rod Programming Optimization in Two-Region Reactors
Hiroshi Motoda, Toshio Kawai
Nuclear Science and Engineering | Volume 39 | Number 1 | January 1970 | Pages 114-118
Technical Note | doi.org/10.13182/NSE70-A21178
Surface Multiplication
R. E. Wilson, R. J. Hall, E. D. Clayton
Nuclear Science and Engineering | Volume 39 | Number 1 | January 1970 | Pages 119-120
Technical Note | doi.org/10.13182/NSE70-A21179
The Influence of the Density Effect on Electron-Induced Cascade Showers in Water and Aluminum
Harold L. Beck
Nuclear Science and Engineering | Volume 39 | Number 1 | January 1970 | Pages 120-121
Technical Note | doi.org/10.13182/NSE70-A21180
Effective Equally Limiting Hot Channels in Reactor Thermal Design
A. Amendola
Nuclear Science and Engineering | Volume 39 | Number 1 | January 1970 | Pages 121-123
Technical Note | doi.org/10.13182/NSE70-A21181
The Effect of Stored Energy on Measurements of Thermal Diffusivity During Irradiation
R. M. Carroll, R. B. Perez, O. Sisman
Nuclear Science and Engineering | Volume 39 | Number 1 | January 1970 | Pages 123-126
Technical Note | doi.org/10.13182/NSE70-A21182
Radiation Heat Transfer in Ceramic Oxide Fuel Elements
J. A. Stoddard, N. J. McCormick
Nuclear Science and Engineering | Volume 39 | Number 1 | January 1970 | Pages 126-129
Technical Note | doi.org/10.13182/NSE70-A21183
Slug-Flow Nusselt Numbers for In-Line Flow Through Unbaffled Rod Bundles
O. E. Dwyer, H. C. Berry
Nuclear Science and Engineering | Volume 39 | Number 2 | February 1970 | Pages 143-150
Technical Paper | doi.org/10.13182/NSE70-A21194
A Variational Approach for the Determination of Neutron Flux Spectra from Detector Activation
R. W. Brandon, J. C. Robinson, C. W. Craven, Jr.
Nuclear Science and Engineering | Volume 39 | Number 2 | February 1970 | Pages 151-162
Technical Paper | doi.org/10.13182/NSE70-A21195
Delayed Neutrons from Low Energy Photofission
L. A. Kull, R. L. Bramblett, T. Gozani, D. E. Rundquist
Nuclear Science and Engineering | Volume 39 | Number 2 | February 1970 | Pages 163-169
Technical Paper | doi.org/10.13182/NSE70-A21196
Neutron Wave Analysis in Finite Media
K. Nishina, A. Z. Akcasu
Nuclear Science and Engineering | Volume 39 | Number 2 | February 1970 | Pages 170-181
Technical Paper | doi.org/10.13182/NSE70-A21197
Neutron Pulse Propagation in a Multiplying Medium
P. K. Doshi, George H. Miley
Nuclear Science and Engineering | Volume 39 | Number 2 | February 1970 | Pages 182-192
Technical Paper | doi.org/10.13182/NSE70-A21198
A Study of the Pulsed Neutron Problem in Ice in the Temperature Range 273 to 21°K
S. P. Tewari, L. S. Kothari
Nuclear Science and Engineering | Volume 39 | Number 2 | February 1970 | Pages 193-206
Technical Paper | doi.org/10.13182/NSE70-A21199
An Adjoint-Weighting in Neutron Fluctuation Analysis with Emphasis on an Effective Detector Efficiency
M. E. Congdon, R. W. Albrecht
Nuclear Science and Engineering | Volume 39 | Number 2 | February 1970 | Pages 207-214
Technical Paper | doi.org/10.13182/NSE70-A21200
Analysis of a Radially Loaded Thermal Reactor
J. C. Vigil, R. J. LaBauve, J. L. Meem
Nuclear Science and Engineering | Volume 39 | Number 2 | February 1970 | Pages 215-225
Technical Paper | doi.org/10.13182/NSE70-A21201
Application of Variational Synthesis to the Optimal Control of Spatially Dependent Reactor Models
W. M. Stacey, Jr.
Nuclear Science and Engineering | Volume 39 | Number 2 | February 1970 | Pages 226-230
Technical Paper | doi.org/10.13182/NSE70-A21202
Digital Control of the Halden Boiling Water Reactor by a Concept Based on Modern Control Theory
T. J. Bjørlo, R. Grumbach, R. Josefsson, K. O. Solberg
Nuclear Science and Engineering | Volume 39 | Number 2 | February 1970 | Pages 231-240
Technical Paper | doi.org/10.13182/NSE70-A21203
On the Use of Point Kinetics for the Analysis of Rod-Ejection Accidents
J. B. Yasinsky
Nuclear Science and Engineering | Volume 39 | Number 2 | February 1970 | Pages 241-256
Technical Paper | doi.org/10.13182/NSE70-A21204
The Beta-Decay Half-Life of 241Pu
Robert G. Nisle, Ivan E. Stepan
Nuclear Science and Engineering | Volume 39 | Number 2 | February 1970 | Pages 257-258
Technical Note | doi.org/10.13182/NSE70-A21205
Self-Absorption of Monoenergetic Electrons in Cobalt Foils
William H. Roach
Nuclear Science and Engineering | Volume 39 | Number 2 | February 1970 | Pages 258-259
Technical Note | doi.org/10.13182/NSE70-A21206
Analysis of the Transmission of 24 keV Neutrons by Gold Spheres Using Spin-Dependent S-Wave Statistics
Thor T. Semler
Nuclear Science and Engineering | Volume 39 | Number 2 | February 1970 | Pages 259-263
Technical Note | doi.org/10.13182/NSE70-A21207
Integral Tests of ENDF/B and GAM Neutron Cross-Section Data in a Clean Fast Assembly
R. A. Moore, D. A. Sargis, S. C. Cohen
Nuclear Science and Engineering | Volume 39 | Number 2 | February 1970 | Pages 263-272
Technical Note | doi.org/10.13182/NSE70-A21208
Polywater as the Mechanism for the pH-Reactivity Effect in Pressurized Water Reactors
Walter H. D'Ardenne
Nuclear Science and Engineering | Volume 39 | Number 2 | February 1970 | Pages 272-273
Technical Note | doi.org/10.13182/NSE70-A21209
Transient Solutions of the Neutron Slowing Down Equation
T. J. Williamson
Nuclear Science and Engineering | Volume 39 | Number 2 | February 1970 | Pages 273-277
Technical Note | doi.org/10.13182/NSE70-A21210
A Variational Rebalancing Method for Linear Iterative Convergence Schemes of Neutron Diffusion and Transport Equations
Shoichiro Nakamura
Nuclear Science and Engineering | Volume 39 | Number 2 | February 1970 | Pages 278-283
Technical Note | doi.org/10.13182/NSE70-A21211
On the Validity of Some Approximate Zero-Power Describing Functions
J. K. Vaurio, G. Pulkkis
Nuclear Science and Engineering | Volume 39 | Number 2 | February 1970 | Pages 283-285
Technical Note | doi.org/10.13182/NSE70-A21212
Boundedness and Stability of Some Models of Nuclear Reactors
Henri B. Smets
Nuclear Science and Engineering | Volume 39 | Number 3 | March 1970 | Pages 289-295
Technical Paper | doi.org/10.13182/NSE70-A19990
Coupled Sampling with the Monte Carlo Method in Neutron Transport Calculations
L. L. Carter, N. J. McCormick
Nuclear Science and Engineering | Volume 39 | Number 3 | March 1970 | Pages 296-310
Technical Paper | doi.org/10.13182/NSE70-A19991
Minimum Critical Mass in Fast Reactors with Bounded Power Density
P. Goldschmidt, J. Quenon
Nuclear Science and Engineering | Volume 39 | Number 3 | March 1970 | Pages 311-319
Technical Paper | doi.org/10.13182/NSE70-A19992
Critical Mass Irregularity of Steel-Moderated Enriched Uranium Metal Assemblies with Composite Steel-Oil Reflectors
Donald C. Coonfield, Grover Tuck, Harold E. Clark, Bruce B. Ernst
Nuclear Science and Engineering | Volume 39 | Number 3 | March 1970 | Pages 320-328
Technical Paper | doi.org/10.13182/NSE70-A19993
Probability Distribution of Neutron Populations in a Multiplying Assembly
D. B. MacMillan
Nuclear Science and Engineering | Volume 39 | Number 3 | March 1970 | Pages 329-336
Technical Paper | doi.org/10.13182/NSE70-A19994
An Analysis of the Neutron Capture Cross Section of 238U Between 1 keV and 15 MeV
W. G. Davey
Nuclear Science and Engineering | Volume 39 | Number 3 | March 1970 | Pages 337-360
Technical Paper | doi.org/10.13182/NSE70-A19995
Fission Cross-Section Ratio Measurements of 239Pu and 233U to 235U from 0.24 to 24 keV
Wayne K. Lehto
Nuclear Science and Engineering | Volume 39 | Number 3 | March 1970 | Pages 361-367
Technical Paper | doi.org/10.13182/NSE70-A19996
Low Flux Measurements of 239Pu and 235U Capture-to-Fission Ratios in a Fast Reactor Spectrum
M. M. Bretscher, W. C. Redman
Nuclear Science and Engineering | Volume 39 | Number 3 | March 1970 | Pages 368-378
Technical Paper | doi.org/10.13182/NSE70-A19997
The Calculation of Gamma-Ray Transition Probabilities in Odd-A Nuclei
K. J. Yost, P. H. Pitkanen, C. Y. Fu
Nuclear Science and Engineering | Volume 39 | Number 3 | March 1970 | Pages 379-386
Technical Paper | doi.org/10.13182/NSE70-A19998
Streamwise Heat Conduction Effects in Forced-Convection Boundary Layers Without and With Superposed Free Convection
E. M. Sparrow, R. P. Heinisch, H. S. Yu
Nuclear Science and Engineering | Volume 39 | Number 3 | March 1970 | Pages 387-393
Technical Paper | doi.org/10.13182/NSE70-A19999
Fast-Reactor-Core Design Optimization by Linear Programming
Kotaro Inoue
Nuclear Science and Engineering | Volume 39 | Number 3 | March 1970 | Pages 394-398
Technical Note | doi.org/10.13182/NSE70-A20000
Outer Iteration Scaling in Neutron Transport Codes
B. E. Clancy, I. J. Donnelly
Nuclear Science and Engineering | Volume 39 | Number 3 | March 1970 | Pages 398-400
Technical Note | doi.org/10.13182/NSE70-A20001
Mullikin's Method for Solving the Neutron Thermalization Nonhomogeneous Equation
I. Caprini, A. Corciovei, V. Protopopescu
Nuclear Science and Engineering | Volume 39 | Number 3 | March 1970 | Pages 401-403
Technical Note | doi.org/10.13182/NSE70-A20002
Extrapolation and Interpolation in Calculation of the Resonance Absorption of Neutrons of Intermediate Energy
Jörn Mikkelsen
Nuclear Science and Engineering | Volume 39 | Number 3 | March 1970 | Pages 403-407
Technical Note | doi.org/10.13182/NSE70-A20003
A Method for Collapsing Fast-Reactor Neutron Cross Sections
M. Pavelescu, V. Anton, I. Purica
Nuclear Science and Engineering | Volume 39 | Number 3 | March 1970 | Pages 407-409
Technical Note | doi.org/10.13182/NSE70-A20004
3He(n,p)T Cross Section from 0.3 to 1.16 MeV
D. G. Costello, S. J. Friesenhahn, W. M. Lopez
Nuclear Science and Engineering | Volume 39 | Number 3 | March 1970 | Pages 409-410
Technical Note | doi.org/10.13182/NSE70-A20005