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Number 1

Table of Contents
Neutron Wave Analysis in Finite Media (K. Nishina, A. Z. Akcasu)
Isune 1: Thermal, Radiation, and Mechanical Analysis for Oxide Fuel Elements of Liquid-Metal Fast Breeder Reactors in Unsteady State (Benjamin M. Ma, C. K Cheng)
Codac (H. Krainer)
TIMOC (H. Kschwendt)
3DDT: A Three-Dimensional Multigroup Diffusion-Burnup Program (John C. Vigil)
Radiation Dosimetry, Volume III (J. E. Turner)
Isospin in Nuclear Physics (Lothar W. Nordheim)
Comments on Adjoint Monte Carlo Sampling Techniques (Leo B. Levitt)

Nonlinear Oscillations and Stability of a Nuclear Reactor with Two Reactivity Feedbacks
Theodore R. Schmidt, David L. Hetrick
Nuclear Science and Engineering | Volume 42 | Number 1 | October 1970 | Pages 1-9
Technical Paper | doi.org/10.13182/NSE70-A19320
Effect of Delayed Neutrons on Autonomous Nonlinear Power Oscillations
Louis M. Shotkin, David L. Hetrick, Theodore R. Schmidt
Nuclear Science and Engineering | Volume 42 | Number 1 | October 1970 | Pages 10-15
Technical Paper | doi.org/10.13182/NSE70-A19321
A Measurement of the Neutronic Interaction Between Two Cylindrical Moderators
G. Grosshög
Nuclear Science and Engineering | Volume 42 | Number 1 | October 1970 | Pages 16-22
Technical Paper | doi.org/10.13182/NSE70-A19322
An Improved Collision Probability Method for Thermal-Neutron-Flux Calculation in a Cylindrical Reactor Cell
T. Boševski
Nuclear Science and Engineering | Volume 42 | Number 1 | October 1970 | Pages 23-27
Technical Paper | doi.org/10.13182/NSE42-01-23
High Resolution Measurements of the Total Neutron Cross Sections of Nitrogen and Iron
A. D. Carlson, R. J. Cerbone
Nuclear Science and Engineering | Volume 42 | Number 1 | October 1970 | Pages 28-40
Technical Paper | doi.org/10.13182/NSE70-A19324
Calculation of the Radiation Hazard at Supersonic Aircraft Altitudes Produced by an Energetic Solar Flare—II
T. W. Armstrong, H. S. Moran
Nuclear Science and Engineering | Volume 42 | Number 1 | October 1970 | Pages 41-48
Technical Paper | doi.org/10.13182/NSE70-A19325
Prediction of Residual Fluxes of Heavy Particles Escaping Radioactive Surfaces
Jacob B. Romero
Nuclear Science and Engineering | Volume 42 | Number 1 | October 1970 | Pages 49-57
Technical Paper | doi.org/10.13182/NSE70-A19326
The Importance of Gravitational Coagulation on the Settling of High-Mass Density Aerosols
G. C. Lindauer, A. W. Castleman, Jr.
Nuclear Science and Engineering | Volume 42 | Number 1 | October 1970 | Pages 58-63
Technical Paper | doi.org/10.13182/NSE70-A19327
Geometry for Efficient External and Internal Cooling of Cylindrical Heat Sources
G. Melese-d'Hospital
Nuclear Science and Engineering | Volume 42 | Number 1 | October 1970 | Pages 64-68
Technical Paper | doi.org/10.13182/NSE70-A19328
Effects of Cladding Thickness and Thermal Conductivity on Heat Transfer for Laminar In-Line Flow Through Rod Bundles
O. E. Dwyer, H. C. Berry
Nuclear Science and Engineering | Volume 42 | Number 1 | October 1970 | Pages 69-80
Technical Paper | doi.org/10.13182/NSE70-A19329
Laminar-Flow Heat Transfer for In-Line Flow Through Unbaffled Rod Bundles
O. E. Dwyer, H. C. Berry
Nuclear Science and Engineering | Volume 42 | Number 1 | October 1970 | Pages 81-88
Technical Paper | doi.org/10.13182/NSE70-A19330
Optimization of Gas-Cooled Fast Reactor Blankets
C. Maeder
Nuclear Science and Engineering | Volume 42 | Number 1 | October 1970 | Pages 89-93
Technical Note | doi.org/10.13182/NSE70-A19331
Space Dependence of the Reactor Kinetic Parameter as Measured by the Garelis-Russell Method
C. Laperches, F. J. Munno
Nuclear Science and Engineering | Volume 42 | Number 1 | October 1970 | Pages 93-97
Technical Note | doi.org/10.13182/NSE70-A19332
Calculations of Neutron Time-Energy Distributions in Heavy Moderators
T. J. Williamson, R. W. Albrecht
Nuclear Science and Engineering | Volume 42 | Number 1 | October 1970 | Pages 97-100
Technical Note | doi.org/10.13182/NSE70-A19333
The Formulation of Continuous Slowing Down Theory for General Processes in Terms of Separable Kernels
Martin Becker, Edward T. Burns
Nuclear Science and Engineering | Volume 42 | Number 1 | October 1970 | Pages 100-103
Technical Note | doi.org/10.13182/NSE70-A19334
On the Discrete Spectrum of the Transport Operator
Pekka Silvennoinen, P. F. Zweifel
Nuclear Science and Engineering | Volume 42 | Number 1 | October 1970 | Pages 103-104
Technical Note | doi.org/10.13182/NSE70-A19335
The Average Angle of Scattering in Energy-Dependent Problems
Frank McGirt, Martin Becker
Nuclear Science and Engineering | Volume 42 | Number 1 | October 1970 | Pages 104-106
Technical Note | doi.org/10.13182/NSE70-A19336
The Effect of Plutonium-241 Decay on the Analysis of Plutonium Critical Experiments
V. O. Uotinen
Nuclear Science and Engineering | Volume 42 | Number 1 | October 1970 | Pages 107-109
Technical Note | doi.org/10.13182/NSE70-A19337
Effective Atomic Numbers for Gamma-Ray Interactions in Alloys
V. Seshagiri Rao, M. N. Seetharamanath, K. Narasimha Murty, K. Parthasaradhi
Nuclear Science and Engineering | Volume 42 | Number 1 | October 1970 | Pages 109-111
Technical Note | doi.org/10.13182/NSE70-A19338

Number 2

Table of Contents
Neutron Spectrum Measurements in a Homogeneous Erbium System and Erbium Cross Sections (T. Gozani, G. D. Trimble)
Total Neutron Cross Section of Technetium-99 from 0.01 to 1000 eV (T. Watanabe, S. D. Reeder)

Time-Dependent Neutron Spectra Measurements in Water
J. H. Menzel, R. E. Slovacek, E. R. Gaerttner
Nuclear Science and Engineering | Volume 42 | Number 2 | November 1970 | Pages 119-136
Technical Paper | doi.org/10.13182/NSE70-A19493
A Calculation of the Coherent Neutron Scattering from Polycrystalline Beryllium
G. M. Borgonovi, D. Sprevak
Nuclear Science and Engineering | Volume 42 | Number 2 | November 1970 | Pages 137-142
Technical Paper | doi.org/10.13182/NSE70-A19494
Neutron Fission and Capture Cross-Section Measurements for Uranium-233 in the Energy Region 0.02 to 1 eV
L. W. Weston, R. Gwin, G. de Saussure, R. W. Ingle, J. H. Todd, C, W. Craven, R. W. Hockenbury, R. C. Block
Nuclear Science and Engineering | Volume 42 | Number 2 | November 1970 | Pages 143-149
Technical Paper | doi.org/10.13182/NSE70-A19495
Exponential Experiments with Lattices of Uranium-233 Oxide and Thorium Oxide in Light and Heavy Water
H. H. Windsor, W. J. Tunney, G. A. Price
Nuclear Science and Engineering | Volume 42 | Number 2 | November 1970 | Pages 150-161
Technical Paper | doi.org/10.13182/NSE70-2
Neutron Transmission Probabilities Across Control Blades Filled with Round Tubes: Formulation and Accuracy
M. Michelini
Nuclear Science and Engineering | Volume 42 | Number 2 | November 1970 | Pages 162-170
Technical Paper | doi.org/10.13182/NSE70-A19497
On the Complete Eigenvalue Spectrum for the Neutron Wave Problem in Multigroup Diffusion Theory
A. K. Ghatak, N. K. Bansal, Om Pal Singh
Nuclear Science and Engineering | Volume 42 | Number 2 | November 1970 | Pages 171-178
Technical Paper | doi.org/10.13182/NSE70-A19498
Conditional Variances Pertinent to Doppler Effect Studies
R. N. Hwang, L. B. Miller
Nuclear Science and Engineering | Volume 42 | Number 2 | November 1970 | Pages 179-190
Technical Paper | doi.org/10.13182/NSE70-A19499
Fission Yields of Over 40 Stable and Long-Lived Fission Products for Thermal Neutron Fissioned ²³³U, ²³⁵U, ²³⁹Pu, and ²⁴¹Pu and Fast Reactor Fissioned ²³⁵U and ²³⁹Pu
F. L. Lisman, R. M. Abernathey, W. J. Maeck, J. E. Rein
Nuclear Science and Engineering | Volume 42 | Number 2 | November 1970 | Pages 191-214
Technical Paper | doi.org/10.13182/NSE70-A19500
Determination of Nuclear Fuel Burnup from Fission Product Analysis
F. L. Lisman, W. J. Maeck, J. E. Rein
Nuclear Science and Engineering | Volume 42 | Number 2 | November 1970 | Pages 215-219
Technical Paper | doi.org/10.13182/NSE70-A19501
The Interaction of Neutronics and Acoustics in a Gaseous Core Nuclear Rocket
Harry McNeill, Martin Becker
Nuclear Science and Engineering | Volume 42 | Number 2 | November 1970 | Pages 220-229
Technical Paper | doi.org/10.13182/NSE70-A19502
An Accurate Determination of the Value of the Hopf q-Function at Infinity
Wendell C. DeMarcus, Robert A. Stokes
Nuclear Science and Engineering | Volume 42 | Number 2 | November 1970 | Pages 230-231
Technical Note | doi.org/10.13182/NSE70-A19503
A Numerical Calculation of the Milne Problem Extrapolation Length
E. Richard Cohen
Nuclear Science and Engineering | Volume 42 | Number 2 | November 1970 | Pages 231-232
Technical Note | doi.org/10.13182/NSE70-A19504
Evaluation of the Mott Scattering Cross Section and the Goudsmit-Saunderson Multiple Scattering Distribution for Electron Transport Calculations
R. M. Felder
Nuclear Science and Engineering | Volume 42 | Number 2 | November 1970 | Pages 232-233
Technical Note | doi.org/10.13182/NSE70-A19505
Calculation of Heterogeneous Fluxes and Reactivity Worths
W. M. Stacey, Jr.
Nuclear Science and Engineering | Volume 42 | Number 2 | November 1970 | Pages 233-236
Technical Note | doi.org/10.13182/NSE70-A19506
Time-Step Length Errors in Digital Simulation of Spatial Xenon Oscillations
Claude G. Poncelet, Alan M. Christie
Nuclear Science and Engineering | Volume 42 | Number 2 | November 1970 | Pages 236-239
Technical Note | doi.org/10.13182/NSE70-A19507
Xenon Oscillation Experiments in a Production Reactor
S. V. Topp, R. F. Byars, R. P. Germann
Nuclear Science and Engineering | Volume 42 | Number 2 | November 1970 | Pages 239-254
Technical Note | doi.org/10.13182/NSE70-A19508

Number 3

Table of Contents
The Chemistry of Uranium (Herbert H. Hyman)
On the Cross-Spectral-Density Sink Frequency Behavior in Coupled Core Reactors (E. Viehl)
Additional Comments on the Cross-Spectral-Density Sink Frequency Behavior for Coupled Core Argonaut Reactors (R. A. Danofsky)
Burnup Optimization of Continuous Scattered Refueling (H. Motoda)

An Extended Equivalence Relation
Charles N. Kelber
Nuclear Science and Engineering | Volume 42 | Number 3 | December 1970 | Pages 257-259
Technical Paper | doi.org/10.13182/NSE70-A21214
On Some Exact and Approximate Solutions of the Neutron Slowing Down Equation in Resonant Absorbing Media
L. Finkelstein, M. Shatz
Nuclear Science and Engineering | Volume 42 | Number 3 | December 1970 | Pages 260-266
Technical Paper | doi.org/10.13182/NSE70-A21215
A Multiple Scattering and Collision Probability Method for Neutron Transport Problems
T. Lefvert
Nuclear Science and Engineering | Volume 42 | Number 3 | December 1970 | Pages 267-271
Technical Paper | doi.org/10.13182/NSE70-A21216
The Effect of Errors in the Delayed-Neutron Data on Fast Reactor Static and Dynamic Calculations
D. Saphier, S. Yiftah
Nuclear Science and Engineering | Volume 42 | Number 3 | December 1970 | Pages 272-277
Technical Paper | doi.org/10.13182/NSE70-A21217
Space-Time Effects in Fast Reactor Dynamics
James F. Jackson, William E. Kastenberg
Nuclear Science and Engineering | Volume 42 | Number 3 | December 1970 | Pages 278-294
Technical Paper | doi.org/10.13182/NSE70-A21218
Phase Space Analysis of Reactor Kinetics
Simon A. Vreeke, Gary M. Sandquist
Nuclear Science and Engineering | Volume 42 | Number 3 | December 1970 | Pages 295-305
Technical Paper | doi.org/10.13182/NSE70-A21219
A General Method of Importance Sampling the Angle of Scattering in Monte Carlo Calculations
Calvin E. Burgart, P. N. Stevens
Nuclear Science and Engineering | Volume 42 | Number 3 | December 1970 | Pages 306-323
Technical Paper | doi.org/10.13182/NSE70-A21220
Secondary Gamma-Ray Production and Transport in Liquid Nitrogen
G. M. Reynolds, S. M. Sperling, W. E. Selph
Nuclear Science and Engineering | Volume 42 | Number 3 | December 1970 | Pages 324-334
Technical Paper | doi.org/10.13182/NSE70-A21221
Gamma-Ray Spectra Arising from Fast-Neutron Interactions in Elements Found in Soils, Concretes, and Structural Materials
R. E. Maerker, F. J. Muckenthaler
Nuclear Science and Engineering | Volume 42 | Number 3 | December 1970 | Pages 335-351
Technical Paper | doi.org/10.13182/NSE70-A21222
Gamma-Ray Production Cross Sections for the ¹⁶O(n,xγ) Reaction from 6.35- to 16.52-MeV Neutron Energy
V. J. Orphan, C. G. Hoot, Joseph John
Nuclear Science and Engineering | Volume 42 | Number 3 | December 1970 | Pages 352-366
Technical Paper | doi.org/10.13182/NSE70-A21223
The Absorbed Dose and Dose Equivalent from Neutrons in the Energy Range 60 to 3000 MeV and Protons in the Energy Range 400 to 3000 MeV
R. G. Alsmiller, Jr., T. W. Armstrong, W. A. Coleman
Nuclear Science and Engineering | Volume 42 | Number 3 | December 1970 | Pages 367-381
Technical Paper | doi.org/10.13182/NSE70-A21224
Analytical Determination of the Neutron Flux-to-Pressur Frequency Response: Application to the Molten-Salt Reactor Experiment
J. C. Robinson
Nuclear Science and Engineering | Volume 42 | Number 3 | December 1970 | Pages 382-396
Technical Paper | doi.org/10.13182/NSE70-A21225
Experimental Neutron Flux-to-Pressure Frequency Response for the Molten-Salt Reactor Experiment: Determination of Void Fraction in Fuel Salt
J. C. Robinson, D. N. Fry
Nuclear Science and Engineering | Volume 42 | Number 3 | December 1970 | Pages 397-405
Technical Paper | doi.org/10.13182/NSE70-A21226
Heat Transfer in Reactor Components Having Temperature-Dependent Thermal Conductivity
E. M. Sparrow, R. N. Koopman
Nuclear Science and Engineering | Volume 42 | Number 3 | December 1970 | Pages 406-414
Technical Paper | doi.org/10.13182/NSE70-A21227
An Approach to the Stability Criterion for a Nuclear Reactor
Masahide Imasaki, Yoshitaka Sueoka
Nuclear Science and Engineering | Volume 42 | Number 3 | December 1970 | Pages 415-418
Technical Note | doi.org/10.13182/NSE70-A21228
A Comparison of P₁ Vacuum Boundary Conditions
Song-Teh Huang, E. E. Lewis
Nuclear Science and Engineering | Volume 42 | Number 3 | December 1970 | Pages 418-419
Technical Note | doi.org/10.13182/NSE70-A21229
Cross-Spectral-Density Sink Frequency Behavior for Coupled-Core Argonaut Reactors
Mohamed El-Sayed Nagy, Richard A. Danofsky
Nuclear Science and Engineering | Volume 42 | Number 3 | December 1970 | Pages 419-421
Technical Note | doi.org/10.13182/NSE70-A21230
The Energy Spectrum of Photoneutrons Produced by 140-MeV Electrons Incident on Tantalum
C. E. Burgart, E. A. Straker, T. A. Love, R. M. Freestone, Jr.
Nuclear Science and Engineering | Volume 42 | Number 3 | December 1970 | Pages 421-423
Technical Note | doi.org/10.13182/NSE70-A21231
Effective Atomic Numbers for Coherent Scattering Process of Gamma Rays in Alloys
M. Sriramachandra Murty, A. Lakshmana Rao, J. Rama Rao, K. Parthasaradhi
Nuclear Science and Engineering | Volume 42 | Number 3 | December 1970 | Pages 423-424
Technical Note | doi.org/10.13182/NSE70-A21232
Electronic Energy Loss by Fission Fragments
Joseph M. Calo
Nuclear Science and Engineering | Volume 42 | Number 3 | December 1970 | Pages 424-426
Technical Note | doi.org/10.13182/NSE70-A21233
An Experimental Demonstration of Inert Gas Effects upon the Incipient Pool Boiling of Sodium
Ralph M. Singer
Nuclear Science and Engineering | Volume 42 | Number 3 | December 1970 | Pages 427-428
Technical Note | doi.org/10.13182/NSE70-A21234