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Volume 78

Number 2

Calculation of the Radial and Axial Diffusion Coefficient for a Hexagonal Lattice of a High-Temperature Reactor with Block Elements

P. Köhler

Nuclear Science and Engineering / Volume 78 / Number 2 / June 1981 / Pages 113-120

Technical Paper / dx.doi.org/10.13182/NSE81-A20097

Criticality of 4.3 wt% Uranium-235 Enriched UO2 Rods in Uranyl Nitrate Solution Containing Gadolinium

R. C. Lloyd, S. R. Bierman, E. D. Clayton, B. M. Durst

Nuclear Science and Engineering / Volume 78 / Number 2 / June 1981 / Pages 121-125

Technical Paper / dx.doi.org/10.13182/NSE81-A20098

Fission-Product Energy Release for Times Following Thermal-Neutron Fission of Plutonium-239 and Plutonium-241 Between 2 and 14 000 s

J. K. Dickens, T. A. Love, J. W. McConnell, R. W. Peelle

Nuclear Science and Engineering / Volume 78 / Number 2 / June 1981 / Pages 126-146

Technical Paper / dx.doi.org/10.13182/NSE81-A20099

Uranium-238 Inelastic Neutron Scattering at 82 keV

R. R. Winters, N. W. Hill, R. L. Macklin, J. A. Harvey, D. K. Olsen, G. L. Morgan

Nuclear Science and Engineering / Volume 78 / Number 2 / June 1981 / Pages 147-153

Technical Paper / dx.doi.org/10.13182/NSE81-A20100

Phenomenological Modeling of the Triggering Phase of Small-Scale Steam Explosion Experiments

M. L. Corradini

Nuclear Science and Engineering / Volume 78 / Number 2 / June 1981 / Pages 154-170

Technical Paper / dx.doi.org/10.13182/NSE81-A20101

Exact Solution for Suboptimal Control of Nuclear Reactors with Distributed Parameters

S. H. Kim, Jonghwa Chang

Nuclear Science and Engineering / Volume 78 / Number 2 / June 1981 / Pages 171-175

Technical Note / dx.doi.org/10.13182/NSE81-A20102

Monte Carlo Self-Shielding Corrections for Use with Neutron Spectrum Unfolding Codes

D. J. Brenner

Nuclear Science and Engineering / Volume 78 / Number 2 / June 1981 / Pages 175-177

Technical Note / dx.doi.org/10.13182/NSE81-A20103

Fast Neutron Spectrum in Lithium with a 14-MeV Neutron Source

A. E. Profio, Gad Shani, G. A. Dissanaike

Nuclear Science and Engineering / Volume 78 / Number 2 / June 1981 / Pages 178-182

Technical Note / dx.doi.org/10.13182/NSE81-A20104

A Determination of the Carbon Thermal Neutron Capture Cross Section

W. V. Prestwich, M. A. Islam, T. J. Kennett

Nuclear Science and Engineering / Volume 78 / Number 2 / June 1981 / Pages 182-185

Technical Note / dx.doi.org/10.13182/NSE81-A20105

Decay Rate and Decay Heat Data from Fission Products

K. Shure

Nuclear Science and Engineering / Volume 78 / Number 2 / June 1981 / Pages 185-190

Technical Note / dx.doi.org/10.13182/NSE81-A20106