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Volume 33

Number 1 | Number 2 | Number 3

Number 1

The Solution of a Diffusion-Convective Corrosion Problem

Dale W. Lick, J. N. Tunstall

Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 1-6

Technical Paper / dx.doi.org/10.13182/NSE68-A20911

An Evaluation of the Departure from Nucleate Boiling in Bundles of Reactor Fuel Rods

L. S. Tong

Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 7-15

Technical Paper / dx.doi.org/10.13182/NSE68-A20912

The Total Neutron Cross Section of 115-Day Tantalum-182 from 0.01 to 1000 eV

G. E. Stokes, R. P. Schuman, and O. D. Simpson

Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 16-23

Technical Paper / dx.doi.org/10.13182/NSE68-A20913

Absolute Radiative Capture Cross Section for Fast Neutrons in 238U

H. O. Menlove and W. P. Poenitz

Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 24-30

Technical Paper / dx.doi.org/10.13182/NSE68-2

Neutron Scattering by Reactor-Grade Graphite

W. L. Whittemore

Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 31-40

Technical Paper / dx.doi.org/10.13182/NSE68-A20915

Slow-Neutron Inelastic Scattering and the Dynamics of Heavy Water

O. K. Harling

Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 41-50

Technical Paper / dx.doi.org/10.13182/NSE68-A20916

Central Reactivity Contributions of 244Cm, 239Pu, and 235U in a Bare Critical Assembly of Plutonium Metal

David Maxwell Barton

Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 51-55

Technical Paper / dx.doi.org/10.13182/NSE68-A20917

Measurement of Reactor Fluctuation Spectra and Subcritical Reactivity

C. W. Ricker, S. H. Hanauer, and E. R. Mann

Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 56-64

Technical Paper / dx.doi.org/10.13182/NSE68-A20918

Thermal-Neutron Decay in Small Systems

J. Dorning

Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 65-80

Technical Paper / dx.doi.org/10.13182/NSE68-A20919

Time-Dependent Neutron Thermalization in Finite Light Water Systems

J. Dorning

Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 81-92

Technical Paper / dx.doi.org/10.13182/NSE68-A20920

A Modal Analysis of Neutron-Flux Spatial Oscillation

Masahide Imasaki and Torao Yanaru

Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 93-105

Technical Paper / dx.doi.org/10.13182/NSE68-A20921

On the Space-Energy Separability of the Fundamental Mode of the Neutron Transport Operator with Isotropic Scattering

Feroz Ahmed, A. K. Ghatak

Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 106-118

Technical Paper / dx.doi.org/10.13182/NSE68-A20922

A Transport Theory of Neutron Wave Propagation in Polycrystalline Media

James J. Duderstadt

Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 119-127

Technical Paper / dx.doi.org/10.13182/NSE68-A20923

A Three-Dimensional PN Spherical Harmonics Theory in Cylindrical Geometry

C. Maeder

Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 128-138

Technical Paper / dx.doi.org/10.13182/NSE68-A20924

Investigation of the Criticality of Low-Enrichment Uranium Cylinders

C. G. Chezem, E. J. Lozito

Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Page 139

Technical Note / dx.doi.org/10.13182/NSE68-A20925

An Interpretation of Reflector Savings Measured in Water-Moderated and Reflected Exponential Experiments

Henry H. Windsor

Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 139-141

Technical Note / dx.doi.org/10.13182/NSE68-A20926

The Approach to the Asymptotic Density of Neutrons Slowing Down from a Delta-Function Source

T. J. Williamson and R. W. Albrecht

Nuclear Science and Engineering / Volume 33 / Number 1 / July 1968 / Pages 141-143

Technical Note / dx.doi.org/10.13182/NSE68-A20927

Number 2

Placzek-Type Oscillations in General Neutron Slowing Down

M. Segev, S. Yiftah

Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 147-150

Technical Paper / dx.doi.org/10.13182/NSE68-A20652

PN Blackness Theory in Plane Geometry

S. P. Congdon, M. R. Mendelson

Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 151-161

Technical Paper / dx.doi.org/10.13182/NSE68-A20653

Optimal Control of Xenon-Power Spatial Transients

Weston M. Stacey, Jr.

Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 162-168

Technical Paper / dx.doi.org/10.13182/NSE68-A20654

The Extrapolation Distance for a Black or Grey Cylindrical Neutron Absorber by the Spherical Harmonics Method

Bruno Pellaud

Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 169-186

Technical Paper / dx.doi.org/10.13182/NSE68-A20655

Slow Neutron Scattering from Water

R. M. Brugger

Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 187-194

Technical Paper / dx.doi.org/10.13182/NSE68-A20656

Inelastic Thermal-Neutron Scattering by Liquid D2O

W. L. Whittemore

Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 195-208

Technical Paper / dx.doi.org/10.13182/NSE68-A20657

Thermal-Neutron Diffusion in Light and Heavy Water

P. B. Parks, D. J. Pellarin, N. H. Prochnow, N. P. Baumann

Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 209-217

Technical Paper / dx.doi.org/10.13182/NSE68-A20658

Measurement of the Decay of Thermal Neutrons in Aqueous Solutions of the Non-1/v Neutron Absorber Cadmium

L. G. Larsson, E. Möller

Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 218-224

Technical Paper / dx.doi.org/10.13182/NSE68-A20659

Determination of Reactor Kinetic Parameters by Photon Observation

Wayne K. Lehto, John M. Carpenter

Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 225-237

Technical Paper / dx.doi.org/10.13182/NSE68-A20660

Spatially Dependent Resonance Neutron Spectra in a Slab of Depleted Uranium

H. M Antunez, J. M. Neill

Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 238-248

Technical Paper / dx.doi.org/10.13182/NSE68-A20661

Description of Anisotropic Scattering in the Double Pl Method by Means of Anisotropy Functions

S. A. W. Gerstl, W. Kofink

Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 249-251

Technical Note / dx.doi.org/10.13182/NSE68-A20662

A Variational Approach to the Selection of the Direction Sets in the Discrete Sn Approximation to Neutron Transport Theory

Pekka Jauho, Heikki Kalli

Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 251-254

Technical Note / dx.doi.org/10.13182/NSE68-A20663

Numerical Solution of the Boltzmann Integral Equation—A Multigroup Benchmark Calculation

K. D. Lathrop

Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 255-257

Technical Note / dx.doi.org/10.13182/NSE68-A20664

Application of Variational Synthesis to the Optimal Control of a Point Reactor Model

Weston M. Stacey, Jr.

Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 257-260

Technical Note / dx.doi.org/10.13182/NSE68-A20665

Analytic Resonance Integral Formulae

N. M. Steen

Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 260-262

Technical Note / dx.doi.org/10.13182/NSE68-A20666

Time and Space Relaxation Constants of Neutrons in a Proton Gas

M. M. R. Williams

Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 262-264

Technical Note / dx.doi.org/10.13182/NSE68-A20667

An Iterative Method for Evaluation of Period Measurements in a Reactor Containing an Intrinsic Neutron Source

F. W. A. Habermann, H. Walze

Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 264-265

Technical Note / dx.doi.org/10.13182/NSE68-A20668

Total Neutron Cross Section of Water

J. M. Neill, J. L. Russell, Jr., J. R. Brown

Nuclear Science and Engineering / Volume 33 / Number 2 / August 1968 / Pages 265-267

Technical Note / dx.doi.org/10.13182/NSE68-A20669

Number 3

Performance of Gas-Cooled Fast Reactors with Artificially Roughened Fuel Elements

Gilbert Melese-d'Hospital

Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 271-283

Technical Paper / dx.doi.org/10.13182/NSE68-A19234

Monte Carlo Integration of the Adjoint Gamma-Ray Transport Equation

M. H. Kalos

Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 284-290

Technical Paper / dx.doi.org/10.13182/NSE68-A19235

Monte Carlo Calculations of the Nucleon-Meson Cascade in Iron Initiated by 1- and 3-GeV Protons and Comparison with Experiment

T. W. Armstrong, R. G. Alsmiller, Jr.

Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 291-296

Technical Paper / dx.doi.org/10.13182/NSE68-A19236

Multigroup Treatment of Neutron Transport in Plane Geometry

T. Yoshimura, S. Katsuragi

Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 297-302

Technical Paper / dx.doi.org/10.13182/NSE68-A19237

On the Quantum-Mechanical Foundations of the Neutron Transport Theory

P. Jauho, D. O. Riska

Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 303-306

Technical Paper / dx.doi.org/10.13182/NSE68-A19238

Solution of the Two-Group Neutron Transport Equation—I

D. R. Metcalf, P. F. Zweifel

Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 307-317

Technical Paper / dx.doi.org/10.13182/NSE68-A19239

Solution of the Two-Group Neutron Transport Equation—II

D. R. Metcalf and P. F. Zweifel

Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 318-326

Technical Paper / dx.doi.org/10.13182/NSE68-A19240

Numerical Solutions of Boundary Value Problems

J. W. Lucey, K. F. Hansen

Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 327-335

Technical Paper / dx.doi.org/10.13182/NSE68-A19241

Hexagonal Lattice Coordinates

Bernard H. Duane

Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 336-339

Technical Paper / dx.doi.org/10.13182/NSE68-A19242

Some Consideration of Dose Buildup Factor for a 60Co Cylindrical Source with Shell-Shaped Shield

Yutaka Furuta, Yoshihiko Kanemori

Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 340-341

Technical Note / dx.doi.org/10.13182/NSE68-A19243

First-Flight Escape Probability for Bodies Containing a Central Black Region

Owen J. Smith, Raymond L. Murray

Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 341-343

Technical Note / dx.doi.org/10.13182/NSE33-03-341

Space-Dependent Effects in Rossi-Alpha Experiments

Tsutomu Iijima, Teruo Sugi, Hideo Ezure, Mineo Kasai

Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 344-348

Technical Note / dx.doi.org/10.13182/NSE68-A19245

Resonance Absorption in a Lump Surrounded by a Homogeneous Medium Containing the Same Resonance Absorber

L. I. Tirén

Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 348-350

Technical Note / dx.doi.org/10.13182/NSE68-A19246

Infinite Dilution Resonance Absorption Integrals of Hafnium

J. W. Rogers, J. J. Scoville

Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 350-352

Technical Note / dx.doi.org/10.13182/NSE68-A19247

An Empirical Study of the Convergence of the Eigenfunction Expansion Method for Investigating Neutron Wave Propagation

R. S. Booth, W. A. Swansiger

Nuclear Science and Engineering / Volume 33 / Number 3 / September 1968 / Pages 352-354

Technical Note / dx.doi.org/10.13182/NSE68-A19248

 
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