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Volume 44

Number 3

Table of Contents
Comments on An Improved Collision Probability Method for Thermal-Neutron-Flux Calculation in a Cylindrical Reactor Cell(J. D. Stewart)
Reply to the Comments of J. D. Stewart on the Calculation of Thermal-Neutron Flux(Tome Boševski)
Collision Probabilities for Finite Cylinders and Cuboids(I. Carlvik)
The Calculation of Gamma-Ray Transition Probabilities in Odd-A Nuclei(K. J. Yost, P. H. Pitkanen, C. Y. Fu)

An Analytical and Experimental Investigation of the Vibration of Cylindrical Reactor Fuel Elements in Two-Phase Parallel Flow

D. J. Gorman

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 277-290

Technical Paper / dx.doi.org/10.13182/NSE71-A20161

A Generalized Local Boiling Void Model for Light-Water Reactor System

William T. Sha

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 291-300

Technical Paper / dx.doi.org/10.13182/NSE71-A20162

Dynamic Stability of Cylindrical Shells Subjected to Sonic Waves Due to a Loss-of-Coolant Reactor Accident

George J. Bohm, Elmar A. Steck

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 301-309

Technical Paper / dx.doi.org/10.13182/NSE71-A20163

Carbon Loss from Graphite Cylinders Exposed to Steam for Short Times

M. Necati Özişik, H. J. de Nordwall

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 310-319

Technical Paper / dx.doi.org/10.13182/NSE71-A20164

A Study of Coolant Transients During a Rapid Fission Gas Release in a Fast Reactor Subassembly

T. C. Chawla, B. M. Hoglund

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 320-344

Technical Paper / dx.doi.org/10.13182/NSE71-A20165

An Evaluation of the Number of Neutrons Per Fission for the Principal Plutonium, Uranium, and Thorium Isotopes

W. G. Davey

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 345-371

Technical Paper / dx.doi.org/10.13182/NSE71-A20166

Effect of Moderation on Reaction Cross-Section Measurements

Melvin M. Levine

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 372-375

Technical Paper / dx.doi.org/10.13182/NSE71-A20167

Fast Neutron Penetration in Paraffin and Lithium Hydride

A. E. Profio, R. J. Cerbone, D. L. Huffman

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 376-387

Technical Paper / dx.doi.org/10.13182/NSE71-A20168

The Measurement of Flux Fine Structure in Plate Fast Reactor Cells of Finite Size

Philip F. Palmedo, Henry H. Windsor

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 388-397

Technical Paper / dx.doi.org/10.13182/NSE71-A20169

An Analysis of Flux Fine Structure in One-Dimensional Fast Reactor Cells

Hans Ludewig

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 398-405

Technical Paper / dx.doi.org/10.13182/NSE71-A20170

Bounded Estimators for Flux at a Point in Monte Carlo

Herbert A. Steinberg, Malvin H. Kalos

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 406-412

Technical Paper / dx.doi.org/10.13182/NSE71-A20171

The Reactivity Effect of Replacing a Water Reflector with Lead

G. Klotzkin, R. F. Valentine, C. A. Flanagan, J. C. Stachew

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 413-422

Technical Paper / dx.doi.org/10.13182/NSE71-A20172

The SP_N-P_L Method for Neutron Transport in Homogeneous Slabs with Anisotropic Scattering

H. Kschwendt

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 423-434

Technical Paper / dx.doi.org/10.13182/NSE71-A20173

The Influence of Power Flattening on Hot Channel Factors

A. Amendola

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 435-437

Technical Note / dx.doi.org/10.13182/NSE71-A20174

Thick Target Yields for the ⁹Be(α, n) Reaction

M. E. Anderson, M. R. Hertz

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 437-439

Technical Note / dx.doi.org/10.13182/NSE71-A20175

Note on the Prompt-Fission-Neutron Spectra of Uranium-235 and Plutonium-239

A. B. Smith

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 439-442

Technical Note / dx.doi.org/10.13182/NSE71-A20176

Approximate Treatments of the Effect of Anisotropy on Elastic Neutron Moderation

Weston M. Stacey, Jr.

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 442-444

Technical Note / dx.doi.org/10.13182/NSE71-A20177

Slowing Down and Heating Up of Neutrons in Graphite at Low Temperatures

Vidya Bhushan, S. K. Trikha

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 444-447

Technical Note / dx.doi.org/10.13182/NSE71-A20178

Adjoint Spectra for Calculating Thermal Group Constants

D. S. Selengut

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 447-449

Technical Note / dx.doi.org/10.13182/NSE71-A20179

A Theorem Concerning Reflection and Transmission from a Nonabsorbing Slab

Raphael Aronson

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 449-450

Technical Note / dx.doi.org/10.13182/NSE71-A20180

Experimental Determination of the Perturbation Denominator in Fast Critical Assemblies

W. C. Redman, M. M. Bretscher

Nuclear Science and Engineering / Volume 44 / Number 3 / June 1971 / Pages 450-453

Technical Note / dx.doi.org/10.13182/NSE71-A20181