American Nuclear Society
Home

Home / Publications / Journals / Nuclear Science and Engineering / Volume 51 / Number 1

Volume 51

Number 1

Fast Reactor Design Optimization System with a Method of Nonlinear Programming

Kotaro Inoue

Nuclear Science and Engineering / Volume 51 / Number 1 / May 1973 / Pages 1-9

Technical Paper / dx.doi.org/10.13182/NSE73-A23252

On the Control of Spatial Xenon Oscillations

A. M. Christie, C. G. Poncelet

Nuclear Science and Engineering / Volume 51 / Number 1 / May 1973 / Pages 10-24

Technical Paper / dx.doi.org/10.13182/NSE73-A23253

Measurement and Evaluation of Total Neutron Cross-Section Minima in Elemental Iron from 24 to 750 keV

K. A. Alfieri, R. C. Block, P. J. Turinsky

Nuclear Science and Engineering / Volume 51 / Number 1 / May 1973 / Pages 25-31

Technical Paper / dx.doi.org/10.13182/NSE73-A23254

Low Energy Components of Scattered Gamma Radiation

Susumu Minato

Nuclear Science and Engineering / Volume 51 / Number 1 / May 1973 / Pages 32-40

Technical Paper / dx.doi.org/10.13182/NSE73-A23255

Evaluation of Lumped Parameter Heat Transfer Techniques for Nuclear Reactor Applications

D. M. France, T. Ginsberg

Nuclear Science and Engineering / Volume 51 / Number 1 / May 1973 / Pages 41-51

Technical Paper / dx.doi.org/10.13182/NSE73-A23256

The Energy Distribution of Delayed Fission Neutrons

S. Shalev, J. M. Cuttler

Nuclear Science and Engineering / Volume 51 / Number 1 / May 1973 / Pages 52-66

Technical Paper / dx.doi.org/10.13182/NSE73-A23257

A New Method of Solving the Multimode Reactor Kinetics Equations

J. C. Turnage

Nuclear Science and Engineering / Volume 51 / Number 1 / May 1973 / Pages 67-76

Technical Note / dx.doi.org/10.13182/NSE73-A23258

On a Multidirectional Modal Representation for Neutron Transport Analysis

A. A. Harms, S. A. Kushneriuk

Nuclear Science and Engineering / Volume 51 / Number 1 / May 1973 / Pages 76-78

Technical Note / dx.doi.org/10.13182/NSE73-A23259

An Exact Analytical Solution of an Elementary Critical Condition

C. E. Siewert

Nuclear Science and Engineering / Volume 51 / Number 1 / May 1973 / Page 78

Technical Note / dx.doi.org/10.13182/NSE73-A23260

A Simple Analytic Transient Flux Expression for Use With Asymptotic Diffusion Theory

L. E. Beghian, I. A. Forbes, V. C. Rogers

Nuclear Science and Engineering / Volume 51 / Number 1 / May 1973 / Pages 78-83

Technical Note / dx.doi.org/10.13182/NSE73-A23261

Absolute Neutron Yields from Alpha-Particle Interaction with Thick Targets of Natural Carbon

J. K. Bair

Nuclear Science and Engineering / Volume 51 / Number 1 / May 1973 / Pages 83-84

Technical Note / dx.doi.org/10.13182/NSE73-A23262

Heat Conduction in the UO2-Cladding Composite Body with Simultaneous Solidification and Melting

Michael Epstein

Nuclear Science and Engineering / Volume 51 / Number 1 / May 1973 / Pages 84-87

Technical Note / dx.doi.org/10.13182/NSE73-A23263