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Volume 33

Number 3

Table of Contents
Neutron-Wave Propagation Through a Crystalline Moderator—I: Beryllium(Feroz Ahmed, P. S. Grover, L. S. Kothari)
TWIGL(J. B. Yasinsky, M. Natelson, L. A. Hageman)
Annual Review of Nuclear Science, Volume 17, 1967(E. Richard Cohen)

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