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Volume 28

Number 1

Table of Contents
Further Comment on the Optimal Shutdown Control(Yoshikuni Shinohara, Jean Valat)
Optimal Shutdown Control(Milton Ash)
Comment on the Optimal Shutdown Control(John J. Roberts, Harold P. Smith, Jr.)
Comments on the Time Optimal Xenon Shutdown Problem(Anthony G. Dewey)
Remarks With Regard to an Article by Tassan(Rudi Stamm'ler)
Answer to Mr. Stamm'ler's Comments on Article on Thermal Spectrum Measurements(S. Tassan)
Thermal Cross Section and Resonance Integrals of Cadmium-114(S. Pearlstein, R. F. Milligan)
The Thermal-Neutron Milne Problem with a Two-Term Degenerate Kernel(M. M. R. Williams)

Use of Hydraulic Models in Nuclear Reactor Design

G. Hetsroni

Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 1-11

Technical Paper / dx.doi.org/10.13182/NSE67-A18661

A Visual and Frictional Pressure-Drop Study of Natural-Circulation Single-Component Two-Phase Flow at Low Pressures

Min-Nan Huang, M. M. El-Wakil

Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 12-19

Technical Paper / dx.doi.org/10.13182/NSE67-A18662

The Use of Spherical UO₂ in a Cermet Fuel Plate

F. C. Robertshaw, R. K. Betts, D. E. Conner

Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 20-33

Technical Paper / dx.doi.org/10.13182/NSE67-A18663

Performance of Pyrolytic Carbon-Coated Uranium Oxide Particles During Irradiation at High Temperature

P. E. Reagan, R. L. Beatty, E. L. Long, Jr.

Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 34-41

Technical Paper / dx.doi.org/10.13182/NSE67-A18664

Irradiation Behavior of Uranium Fuel Tubes in a Pressurized Heavy-Water Reactor

C. L. Angerman, W. R. McDonell

Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 42-50

Technical Paper / dx.doi.org/10.13182/NSE67-A18665

The Compatibility of Graphite with Cesium

F. J. Salzano, S. Aronson

Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 51-54

Technical Paper / dx.doi.org/10.13182/NSE67-A18666

Beta Particle Backscattering

Thomas S. Bustard, Joseph Silverman

Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 55-61

Technical Paper / dx.doi.org/10.13182/NSE67-A18667

Measurement of Fissions Produced in Bulk Plutonium-239 by 2-eV to 10-keV Neutrons

J. B. Czirr, R. L. Bramblett

Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 62-71

Technical Paper / dx.doi.org/10.13182/NSE67-A18668

Power Oscillations and the Describing Function in Reactors with Linear Feedback

A. Ziya Akcasu, Louis M. Shotkin

Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 72-81

Technical Paper / dx.doi.org/10.13182/NSE67-A18669

The Application of a Hybrid Computer to the Analysis of Transient Phenomena in a Fast Reactor Core

C. K. Sanathanan, J. C. Carter, L. T. Bryant, L. W. Amiot

Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 82-92

Technical Paper / dx.doi.org/10.13182/NSE67-A18670

Solution of Group-Diffusion Equation Using Green's Function

Keisuke Kobayashi, Hiroshi Nishihara

Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 93-104

Technical Paper / dx.doi.org/10.13182/NSE67-A18671

An Analogy Between Time-Dependent Diffusion Theory and Classical Mechanics

B. E. Clancy, M. Tavel

Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 105-110

Technical Paper / dx.doi.org/10.13182/NSE67-A18672

Inelastic Scattering Measurements in a Fast Reactor by the Spherical Shell Method

William G. Davey, Paul I. Amundson

Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 111-123

Technical Paper / dx.doi.org/10.13182/NSE67-A18673

Anisotropic Scattering Coefficients in the Constant Cross-Section Transport Equation

Raymond L. Murray, Charles E. Siewert, Walter J. Harrington

Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 124-126

Technical Paper / dx.doi.org/10.13182/NSE67-A18674

The Effect of Anisotripic Scattering in Plane-Geometry Transport Theory and Monte Carlo Calculations

M. R. Mendelson

Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 127-132

Technical Paper / dx.doi.org/10.13182/NSE67-A18675

Total Neutron Cross Section of Protactinium-233

F. B. Simpson, J. W. Codding, Jr.

Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 133-138

Technical Paper / dx.doi.org/10.13182/NSE67-A18676

The Thermal-Neutron Capture Cross Section of 147Sm

L. Forman, F. A. White

Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 139-143

Technical Paper / dx.doi.org/10.13182/NSE67-A18677

Dose Buildup Factors of Plane Parallel Barriers For 137Cs Plane Monodirectional Source

Kozo Tamura, Akira Tsuruo

Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 144-145

Technical Note / dx.doi.org/10.13182/NSE67-A18678

Method for Calculating Average Thermal Neutron Parameters

J. J. Bulmer, P. B. Daitch

Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 145-148

Technical Note / dx.doi.org/10.13182/NSE67-A18679

Comment on the Calculation of the Scattering Cross Section for Multiple Resonances

John M. Otter

Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 149-150

Technical Note / dx.doi.org/10.13182/NSE67-A18680

A Limitation of the Roussopoulos Variational Principle?

G. C. Pomraning

Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 150-152

Technical Note / dx.doi.org/10.13182/NSE67-A18681

Asymptotic Neutron Pulse Velocity and the System Dispersion Law

M. N. Moore

Nuclear Science and Engineering / Volume 28 / Number 1 / April 1967 / Pages 152-154

Technical Note / dx.doi.org/10.13182/NSE67-A18682