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Volume 42

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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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NSE70-A21234