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Number 1

Table of Contents
Comments on the Iterative Approach to a Space-Time Nonlinear Problem (H. Ibarra)
Reply to Comments on the Iterative Approach to a Space-Time Nonlinear Problem (Louis M. Shotkin)
Comments on Theoretical and Experimental Criteria for Reactor Stability (F. Di Pasquantemio, F. Kappel)
Comments on the Neutron Transport Theory with Anisotropic Scattering (K. O. Thielheim, K. Claussen)
WANSY (J. B. Yasinsky, J. W. Marinacci, A. V. Vota)
Advantages of Using a Combination Electromagnetic and Material Shield (R. D. SHELTON, H. E. STERN, J. W. WATTS)
Computer Code Abstract Citation (T. B. Fowler, D. R. Vondy)
Annual Review of Nuclear Science, Volume 18 (Lothar W. Nordheim)
Engineering Compendium on Radiation Shielding, Vol. 1: Shielding Fundamentals, and Methods (Herbert Goldstein)

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

Number 2

Table of Contents

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

Number 3

Table of Contents
PHENIX: A Two-Dimensional Diffusion-Burnup-Refueling Code (R. Douglas O'Dell, Thomas J. Hirons)
The Space Dependence of Reactor Noise-II Calculations (James R. Sheff, Robert W. Albrecht)

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