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Home / Publications / Journals / Nuclear Science and Engineering / Volume 7 / Number 3

Volume 7

Number 3

Table of Contents
A Method for Interpolation in Moderator to Fuel Ratio Dependent Bucklings(J. Thie)
Delayed Neutron Effects During Flux Tilt Transients(S. Kaplan, S. G. Margolis)
Analysis of Neutron Flux Data for Accurate Determination of Relaxation Length(Leo Seren, Denis Tsakarissianos)

Measurement of Air Blast Effects from Simulated Nuclear Reactor Core Excursions

Wendell C. Olson, Richard J. Larson, Harry Goldstein

Nuclear Science and Engineering / Volume 7 / Number 3 / March 1960 / Pages 199-209

Technical Paper / dx.doi.org/10.13182/NSE60-A25703

The Decay of a Thermalized Neutron Pulse

Mark Nelkin

Nuclear Science and Engineering / Volume 7 / Number 3 / March 1960 / Pages 210-216

Technical Paper / dx.doi.org/10.13182/NSE60-A25704

Methods and Cross Sections for Calculating the Fast Effect

Morton R. Fleishman, Harry Soodak

Nuclear Science and Engineering / Volume 7 / Number 3 / March 1960 / Pages 217-227

Technical Paper / dx.doi.org/10.13182/NSE60-A25705

Neutron Absorption by Control Rods of Varying Transparency

H. Überall

Nuclear Science and Engineering / Volume 7 / Number 3 / March 1960 / Pages 228-234

Technical Paper / dx.doi.org/10.13182/NSE60-A25706

A Useful Analogy for Single-Group Neutron Diffusion Theory

James R. Melcher

Nuclear Science and Engineering / Volume 7 / Number 3 / March 1960 / Pages 235-239

Technical Paper / dx.doi.org/10.13182/NSE60-A25707

Slowing Down of Neutrons in Graphite Close to Thermal Equilibrium

L. S. Kothari, P. G. Khubchandani

Nuclear Science and Engineering / Volume 7 / Number 3 / March 1960 / Pages 240-244

Technical Paper / dx.doi.org/10.13182/NSE60-A25708

Correlation of Burnout Heat-Flux Data at 2000 psia

Donald W. Bell

Nuclear Science and Engineering / Volume 7 / Number 3 / March 1960 / Pages 245-251

Technical Paper / dx.doi.org/10.13182/NSE60-A25709

Calculation of the Effective Resonance Integral of U²³⁸

A. R. Vernon

Nuclear Science and Engineering / Volume 7 / Number 3 / March 1960 / Pages 252-259

Technical Paper / dx.doi.org/10.13182/NSE60-A25710

Comparison Theorems for the Estimation of Average Collision Probabilities. II

Lawrence Dresner

Nuclear Science and Engineering / Volume 7 / Number 3 / March 1960 / Pages 260-262

Technical Paper / dx.doi.org/10.13182/NSE60-A25711

Experimental Check of a Monte Carlo-Calculated Distribution of Resonance Neutron Capture in a Gold Rod

Judson Hardy, Jr., G. G. Smith, D. Klein

Nuclear Science and Engineering / Volume 7 / Number 3 / March 1960 / Pages 263-267

Technical Paper / dx.doi.org/10.13182/NSE60-A25712

The Time-Dependent Importance of Neutrons and Precursors

Jeffery Lewins

Nuclear Science and Engineering / Volume 7 / Number 3 / March 1960 / Pages 268-274

Technical Paper / dx.doi.org/10.13182/NSE60-A25713

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