ANS / Publications / Journals / Nuclear Science and Engineering

Characteristics of the Aerosol Produced from Burning Sodium and Plutonium

Harry J. Ettinger, William D. Moss, Harold Busey

Nuclear Science and Engineering / Volume 30 / Number 1 / October 1967 / Pages 1-13

Technical Paper / dx.doi.org/10.13182/NSE67-A17237

Reactor Organic Coolants II: Electron-Irradiation Studies of Hydrogenated Terphenyls

M. Tomlinson, R. R. Tymko, Donna Wuschke

Nuclear Science and Engineering / Volume 30 / Number 1 / October 1967 / Pages 14-19

Technical Paper / dx.doi.org/10.13182/NSE67-A17238

A Sol-Gel Thorium Oxide with Improved Dissolving Characteristics

E. R. Russell, M. L. Hyder, W. E. Prout, C. B. Goodlett

Nuclear Science and Engineering / Volume 30 / Number 1 / October 1967 / Pages 20-24

Technical Paper / dx.doi.org/10.13182/NSE67-A17239

The Stability of Boiling-Water Reactors and Loops

L. G. Neal, S. M. Zivi

Nuclear Science and Engineering / Volume 30 / Number 1 / October 1967 / Pages 25-38

Technical Paper / dx.doi.org/10.13182/NSE67-A17240

A Study of Fission-Neutron Spectra with High-Energy Activation Detectors—Part I. Detector Development and Excitation Measurements

James A. Grundl

Nuclear Science and Engineering / Volume 30 / Number 1 / October 1967 / Pages 39-53

Technical Paper / dx.doi.org/10.13182/NSE67-A17241

Theory of Branching Processes of Neutrons in a Multiplying Medium

Keiichi Saito, Yukichi Taji

Nuclear Science and Engineering / Volume 30 / Number 1 / October 1967 / Pages 54-64

Technical Paper / dx.doi.org/10.13182/NSE67-A17242

Investigation of Differential Energy and Angle for ¹³⁷Cs Gamma Rays in Water and Air

Mary Alberg, Harold Beck, Keran O'Brien, James E. McLaughlin

Nuclear Science and Engineering / Volume 30 / Number 1 / October 1967 / Pages 65-74

Technical Paper / dx.doi.org/10.13182/NSE67-A17243

Position-Dependent Neutron Spectra in a Multiplying Medium

R. J. Cerbone, R. E. Slovacek, E. R. Gaerttner

Nuclear Science and Engineering / Volume 30 / Number 1 / October 1967 / Pages 75-84

Technical Paper / dx.doi.org/10.13182/NSE67-A17244

Anisotropic Scattering in Cell Problems

Pierre Benoist

Nuclear Science and Engineering / Volume 30 / Number 1 / October 1967 / Pages 85-94

Technical Paper / dx.doi.org/10.13182/NSE67-A17245

Eigenfunction Analysis of Neutron-Wave Propagation in Moderating Media

M. J. Ohanian, R. S. Booth, R. B. Perez

Nuclear Science and Engineering / Volume 30 / Number 1 / October 1967 / Pages 95-103

Technical Paper / dx.doi.org/10.13182/NSE67-A17246

The Delayed-Neutron Fraction—Neutron Lifetime Ratio in a TRIGA Reactor from Noise Analysis

Bruno Bärs

Nuclear Science and Engineering / Volume 30 / Number 1 / October 1967 / Pages 104-108

Technical Paper / dx.doi.org/10.13182/NSE67-A17247

The Fast-Fission Effect in Lattices Consisting of Clustered Elements

Jacques Rognon

Nuclear Science and Engineering / Volume 30 / Number 1 / October 1967 / Pages 109-121

Technical Paper / dx.doi.org/10.13182/NSE67-A17248

Thermal Disadvantage Factors and Fast Advantage Factors in Uranium-Thorium, Seed-Blanket Assemblies

S. S. Glickstein, P. H. Lehmann, L. L. Wheat, J. D. Korsmeyer, S. Milani, G. G. Smith, S. H. Weiss

Nuclear Science and Engineering / Volume 30 / Number 1 / October 1967 / Pages 122-136

Technical Paper / dx.doi.org/10.13182/NSE67-A17249

Neutron Leakage Effects on the Fast Advantage Factor in a Seed-Blanket Assembly

S. S. Glickstein, J. W. Beck, L. L. Wheat, W. J. Hall

Nuclear Science and Engineering / Volume 30 / Number 1 / October 1967 / Pages 137-143

Technical Paper / dx.doi.org/10.13182/NSE67-A17250

Molybdenum-99 Half-life Determination

M. N. Baldwin

Nuclear Science and Engineering / Volume 30 / Number 1 / October 1967 / Page 144

Technical Note / dx.doi.org/10.13182/NSE67-A17251

The Total Neutron Cross Section of Palladium from 0.005 to 10 eV

M. C. Teich, P. J. Schweitzer, C. A. Anderson, T. J. Thompson

Nuclear Science and Engineering / Volume 30 / Number 1 / October 1967 / Page 145

Technical Note / dx.doi.org/10.13182/NSE30-01-145TN

Iteration and Intermediate Resonance Absorption

Rubin Goldstein

Nuclear Science and Engineering / Volume 30 / Number 1 / October 1967 / Page 146

Technical Note / dx.doi.org/10.13182/NSE67-A17253

Effects of Moderator Temperature Gradients on Thermal-Neutron Flux

Michael D. Williams, Thomas E. Hicks

Nuclear Science and Engineering / Volume 30 / Number 1 / October 1967 / Pages 147-150

Technical Note / dx.doi.org/10.13182/NSE67-A17254

Collision Probabilities for Finite Cylinders and Cuboids

I. Carlvik

Nuclear Science and Engineering / Volume 30 / Number 1 / October 1967 / Pages 150-151

Technical Note / dx.doi.org/10.13182/NSE30-01-150TN

Convergence of the Source Iteration Technique in Solution of the Multigroup Neutron Transport or Diffusion Equations with External Source

N. Spinks

Nuclear Science and Engineering / Volume 30 / Number 1 / October 1967 / Pages 152-154

Technical Note / dx.doi.org/10.13182/NSE67-A17256

Solvent Effects on Reaction Rates and Mechanisms

M. Lee Hyder

Nuclear Science and Engineering / Volume 30 / Number 1 / October 1967 / Page 156

Book Review / dx.doi.org/10.13182/NSE67-A17259

Optimal Shutdown Control of Nuclear Reactors

John J. Roberts

Nuclear Science and Engineering / Volume 30 / Number 1 / October 1967 / Pages 156-157

Book Review / dx.doi.org/10.13182/NSE67-A17260

Thermal Stress and Low-Cycle Fatigue

S. H. Fistedis

Nuclear Science and Engineering / Volume 30 / Number 1 / October 1967 / Pages 157-158

Book Review / dx.doi.org/10.13182/NSE67-A17261

Health Physics, Principles of Radiation Protection

Newton Underwood

Nuclear Science and Engineering / Volume 30 / Number 1 / October 1967 / Page 158

Book Review / dx.doi.org/10.13182/NSE67-A17262

Truncation of the Spherical Harmonic Expansion of the Transport Equation

Roger B. DeBar

Nuclear Science and Engineering / Volume 30 / Number 2 / November 1967 / Pages 159-165

Technical Paper / dx.doi.org/10.13182/NSE67-A17326

A Perturbation Method Which Utilizes the Variational Principles Associated with the Neutron Diffusion Equation

Richard E. Turley

Nuclear Science and Engineering / Volume 30 / Number 2 / November 1967 / Pages 166-175

Technical Paper / dx.doi.org/10.13182/NSE67-A17327

A Black-White Model for Including Epithermal Absorption in Calculations of Control-Rod Worth

N. Spinks

Nuclear Science and Engineering / Volume 30 / Number 2 / November 1967 / Pages 176-181

Technical Paper / dx.doi.org/10.13182/NSE67-A17328

An Analysis of the Mutual Interaction of Circumferential Control Plates

N. Spinks

Nuclear Science and Engineering / Volume 30 / Number 2 / November 1967 / Pages 182-187

Technical Paper / dx.doi.org/10.13182/NSE67-A17329

Reactor Noise in Heterogeneous Systems: I. Plate-Type Elements

M. M. R. Williams

Nuclear Science and Engineering / Volume 30 / Number 2 / November 1967 / Pages 188-198

Technical Paper / dx.doi.org/10.13182/NSE67-A17330

Multiple Scattering in Slow-Neutron Double-Differential Measurements

E. L. Slaggie

Nuclear Science and Engineering / Volume 30 / Number 2 / November 1967 / Pages 199-212

Technical Paper / dx.doi.org/10.13182/NSE67-A17331

Spatial Distributions in Water of Neutrons from a 2.85-MeV T(ρ,n)³He Source

R. W. Stooksberry, E. E. Carroll, Jr.

Nuclear Science and Engineering / Volume 30 / Number 2 / November 1967 / Pages 213-221

Technical Paper / dx.doi.org/10.13182/NSE67-A17332

Atom Ratios and Effective Cross-Section Ratios in Highly Depleted Plutonium-Aluminum Alloy Fuel

W. A. Reardon, D. E. Christensen

Nuclear Science and Engineering / Volume 30 / Number 2 / November 1967 / Pages 222-232

Technical Paper / dx.doi.org/10.13182/NSE67-A17333

Ionization by Fission Fragments Escaping from a Source Medium

Dong H. Nguyen, Lawrence M. Grossman

Nuclear Science and Engineering / Volume 30 / Number 2 / November 1967 / Pages 233-241

Technical Paper / dx.doi.org/10.13182/NSE67-A17334

The Study of Thermal Neutrons in Shields Containing Ducts by Source-Separation Techniques

F. R. Channon, R. L. Seale

Nuclear Science and Engineering / Volume 30 / Number 2 / November 1967 / Pages 242-260

Technical Paper / dx.doi.org/10.13182/NSE67-A17335

Experimental Studies on Gamma-Ray Dose Rates from a ⁶⁰Co Cylindrical Source

Yutaka Furuta, Yoshihiko Kanemori

Nuclear Science and Engineering / Volume 30 / Number 2 / November 1967 / Pages 261-267

Technical Paper / dx.doi.org/10.13182/NSE67-A17336

An Analytical Investigation of the Transient Response of the Volumetric Concentration in a Boiling Forced-Flow System

Novak Zuber, F. W. Staub

Nuclear Science and Engineering / Volume 30 / Number 2 / November 1967 / Pages 268-278

Technical Paper / dx.doi.org/10.13182/NSE67-A17337

Experimental Investigation of the Transient Response of the Volumetric Concentration in a Boiling Forced-Flow System

F. W. Staub, N. Zuber, G. Bijwaard

Nuclear Science and Engineering / Volume 30 / Number 2 / November 1967 / Pages 279-295

Technical Paper / dx.doi.org/10.13182/NSE67-A17338

Void Response to Flow and Power Oscillations in a Forced-Convection Boiling System with Axially Nonuniform Power Input

F. W. Staub, N. Zuber

Nuclear Science and Engineering / Volume 30 / Number 2 / November 1967 / Pages 296-303

Technical Paper / dx.doi.org/10.13182/NSE67-A17339

Intermediate Resonance Absorption for Multi-Nuclide Systems

Rubin Goldstein

Nuclear Science and Engineering / Volume 30 / Number 2 / November 1967 / Page 304

Technical Note / dx.doi.org/10.13182/NSE67-A17340

An Improvement of the S_N Calculation Method for Slab Geometry

J. J. Wagschal

Nuclear Science and Engineering / Volume 30 / Number 2 / November 1967 / Pages 305-307

Technical Note / dx.doi.org/10.13182/NSE67-A17341

An Expression for the Remainder in the Spherical Harmonics Method

W. L. Hendry

Nuclear Science and Engineering / Volume 30 / Number 2 / November 1967 / Pages 307-308

Technical Note / dx.doi.org/10.13182/NSE67-A17342

Neutron Emission Growth in Plutonium-Beryllium Sources

E. D. Jordan, W. H. Bedenbaugh, T. E. Carew

Nuclear Science and Engineering / Volume 30 / Number 2 / November 1967 / Pages 308-309

Technical Note / dx.doi.org/10.13182/NSE67-A17343

Compatibility of Type-304 Stainless Steel with Sodium Paste Reactor Fuels

M. G. Chasanov

Nuclear Science and Engineering / Volume 30 / Number 2 / November 1967 / Pages 310-311

Technical Note / dx.doi.org/10.13182/NSE67-A17344

Thermoelastic Dynamics of a Pulse Reactor

David Burgreen

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 317-327

Technical Paper / dx.doi.org/10.13182/NSE67-A18395

The Use of Infinite Medium Spectra in Gamma-Ray Heating Calculations

T. E. Dudley, M. R. Mendelson, N. E. Holden

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 328-339

Technical Paper / dx.doi.org/10.13182/NSE67-A18396

Neutron Fluxes in Concrete Ducts Arising from Incident Epicadmium Neutrons: Calculations and Experiments

R. E. Maerker, F. J. Muckenthaler

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 340-354

Technical Paper / dx.doi.org/10.13182/NSE67-A18397

Neutron Total and Absorption Cross Sections of ²³⁸Pu

T. E. Young, F. B. Simpson, J. R. Berreth, M. S. Coops

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 355-361

Technical Paper / dx.doi.org/10.13182/NSE67-A18398

Decay of Thermalized Neutron Fields in Graphite

C. H. Reed, C. N. Henry, A. A. Usner

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 362-373

Technical Paper / dx.doi.org/10.13182/NSE67-A18399

Activation Measurement of the Doppler Effect for ²³⁸U Capture and ²³⁵U Fission in a Fast-Neutron Spectrum

G. R. Pflasterer, Jr., R. Sher

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 374-394

Technical Paper / dx.doi.org/10.13182/NSE67-A18400

Reactor Analysis by Monte Carlo

H. Rief, H. Kschwendt

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 395-418

Technical Paper / dx.doi.org/10.13182/NSE67-A18401

Application of the Natural Mode Approximation to Space-Time Reactor Problems

Larry R. Foulke, Elias P. Gyftopoulos

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 419-435

Technical Paper / dx.doi.org/10.13182/NSE67-A18402

Sinusoidal Analysis of a Low-Power Nuclear Reactor by the Wentzel-Kramers-Brillouin Approach

Sevim Tan

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 436-447

Technical Paper / dx.doi.org/10.13182/NSE67-A18403

Variational Functionals for Space-Time Neutronics

Weston M. Stacey, Jr.

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 448-451

Technical Note / dx.doi.org/10.13182/NSE67-A18404

A Perturbation Method for Analysis of Neutron-Source-Worth Experiments in Nuclear Reactors

A. Gandini

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 451-453

Technical Note / dx.doi.org/10.13182/NSE67-A18405

Linear Analysis of Xenon Spatial Oscillations

Weston M. Stacey, Jr.

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 453-455

Technical Note / dx.doi.org/10.13182/NSE67-A18406

Neutron Diffusion Using a Modulated Source

G. A. Massel, M. R. Feix

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 455-458

Technical Note / dx.doi.org/10.13182/NSE67-A18407

A Very Low-Temperature Nuclear Reactor

S. A. Dupree

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 458-461

Technical Note / dx.doi.org/10.13182/NSE67-A18408

Total Gamma Energy Release Due to Thermal-Neutron Fission in ²³⁵U

N. E. Holden, M. R. Mendelson, T. E. Dudley

Nuclear Science and Engineering / Volume 30 / Number 3 / December 1967 / Pages 461-463

Technical Note / dx.doi.org/10.13182/NSE67-A18409