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Volume 44

Number 2

Maximizing the Average Fuel Burnup Over Entire Core: A Poison Management Optimization Problem for Multizone Light-Water Reactor Cores

Atsuyuki Suzuki, Ryohei Kiyose

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 121-134

Technical Paper / dx.doi.org/10.13182/NSE71-A19662

An Integrated Model for Analyzing Disruptive Accidents in Fast Reactors

William T. Sha, Alan E. Waltar

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 135-156

Technical Paper / dx.doi.org/10.13182/NSE71-A19663

Calculations of Weapon Radiation Doses in Single-Compartment Aboveground Concrete Structures

L. G. Mooney

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 157-172

Technical Paper / dx.doi.org/10.13182/NSE71-A19664

Measurement of the Delayed-Neutron Fractions for Thermal Fission of Uranium-235, Plutonium-239, and Uranium-233

John F. Conant, Philip F. Palmedo

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 173-179

Technical Paper / dx.doi.org/10.13182/NSE71-A19665

Epithermal Measurements of Capture and Fission Resonance Integrals in 235U, 233U, 239Pu, and 241Pu

H. M. Eiland, L. J. Esch, F. Feiner, J. L. Mewherter

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 180-189

Technical Paper / dx.doi.org/10.13182/NSE71-A19666

Neutron Yield from the (α, n) Reaction in the Isotope Oxygen-18

Mojtaba Taherzadeh

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 190-193

Technical Paper / dx.doi.org/10.13182/NSE71-A19667

The Effect of Anisotropic Scattering Upon the Elastic Moderation of Fast Neutrons

Weston M. Stacey, Jr.

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 194-203

Technical Paper / dx.doi.org/10.13182/NSE71-A19668

Synthesis of Fast Reactor Space-Energy Neutron Fluxes

P. A. Ombrellaro

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 204-220

Technical Paper / dx.doi.org/10.13182/NSE71-A19669

Measurements and Calculations of Neutron Migration and its Anisotropy in Lattices of Fuel Rods and Liquid Coolant

D. R. Harris, J. A. Mitchell

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 221-238

Technical Paper / dx.doi.org/10.13182/NSE71-A19670

Application of Alternating-Direction Implicit Methods to the Space-Dependent Kinetics Equations

A. L. Wight, K. F. Hansen, D. R. Ferguson

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 239-251

Technical Paper / dx.doi.org/10.13182/NSE71-A19671

Neutron Streaming Through Ducts—Analysis of Experimental Results

Y. T. Song, C. M. Huddleston, A. B. Chilton

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 252-261

Technical Note / dx.doi.org/10.13182/NSE71-A19672

An Improved Method for Calculating Foil Perturbation Effects

Darrell F. Newman

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 261-266

Technical Note / dx.doi.org/10.13182/NSE71-A19673

Values of Eta of Uranium-233, Uranium-235, and Plutonium-239 from Critical Experiments and Reactivity Measurements

D. W. Magnuson

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 266-267

Technical Note / dx.doi.org/10.13182/NSE71-A19674

Optimization of Nuclear Systems by Geometric Programming

G. D. Bouchey, C. S. Beightler, B. V. Koen

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 267-272

Technical Note / dx.doi.org/10.13182/NSE71-A19675

Some Comments on Perturbation Theory

D. S. Selengut

Nuclear Science and Engineering / Volume 44 / Number 2 / May 1971 / Pages 272-275

Technical Note / dx.doi.org/10.13182/NSE71-A19676