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Volume 84

Number 2

The Critical Problem for an Infinite Cylinder

J. R. Thomas, Jr., J. D. Southers, C. E. Siewert

Nuclear Science and Engineering / Volume 84 / Number 2 / June 1983 / Pages 79-82

Technical Paper / dx.doi.org/10.13182/NSE83-A17715

Error Due to Nuclear Data Uncertainties in the Prediction of Large Liquid-Metal Fast Breeder Reactor Core Performance Parameters

Takanobu Kamei, Tadashi Yoshida

Nuclear Science and Engineering / Volume 84 / Number 2 / June 1983 / Pages 83-97

Technical Paper / dx.doi.org/10.13182/NSE83-1

Neutron Capture Cross Sections of 182W, 183W, 184W, and 186W from 2.6 to 2000 keV

R. L. Macklin, D. M. Drake, E. D. Arthur

Nuclear Science and Engineering / Volume 84 / Number 2 / June 1983 / Pages 98-119

Technical Paper / dx.doi.org/10.13182/NSE83-A17717

Model of the Deposition of Colloidal Crud Particles on the Fuel Elements of Nuclear Power Plants

Guillermo A. Urrutia, Susana I. Passaggio, A. J. G. Maroto, Miguel A. Blesa

Nuclear Science and Engineering / Volume 84 / Number 2 / June 1983 / Pages 120-130

Technical Paper / dx.doi.org/10.13182/NSE83-A17718

Boiling and Dryout Behavior in a Liquid-Metal Fast Breeder Reactor Subassembly Bundle Under Low Heat Flux and Low Flow Conditions

M. Ishii, H. K. Fauske

Nuclear Science and Engineering / Volume 84 / Number 2 / June 1983 / Pages 131-146

Technical Paper / dx.doi.org/10.13182/NSE83-A17719

On the Thermal Neutron Transport Processes in Liquid H2O-D2O Mixtures

R. M. Bansal, S. P. Tewari

Nuclear Science and Engineering / Volume 84 / Number 2 / June 1983 / Pages 147-150

Technical Note / dx.doi.org/10.13182/NSE83-A17720

Higher Order Effects in Time-Dependent Sensitivity Problems

G. Palmiotti, M. Salvatores, J. C. Estiot, G. Granget

Nuclear Science and Engineering / Volume 84 / Number 2 / June 1983 / Pages 150-155

Technical Note / dx.doi.org/10.13182/NSE83-A17721

Characterization of Neutron Leakage Probability, keff, and Critical Core Surface Mass Density of Small Reactor Assemblies Through the Trombay Criticality Formula

Anil Kumar, M. Srinivasan, K. Subba Rao

Nuclear Science and Engineering / Volume 84 / Number 2 / June 1983 / Pages 155-164

Technical Note / dx.doi.org/10.13182/NSE83-A17722

New Approximations of Anisotropic Scattering in Neutron Transport and Diffusion Equations

T. Duracz, R. Zelazny

Nuclear Science and Engineering / Volume 84 / Number 2 / June 1983 / Pages 164-166

Technical Note / dx.doi.org/10.13182/NSE83-A17723

A Drift-Flux Model Flow-Regime Map of Two-Phase Flows for Thermal-Hydraulic Calculations

S. Kaizerman, E. Wacholder, E. Elias

Nuclear Science and Engineering / Volume 84 / Number 2 / June 1983 / Pages 166-168

Technical Note / dx.doi.org/10.13182/NSE83-A17724

Characteristics Analysis of Inhomogeneous, Nonequilibrium, Two-Phase Flows Using the Drift-Flux Model

S. Kaizerman, E. Wacholder, E. Elias

Nuclear Science and Engineering / Volume 84 / Number 2 / June 1983 / Pages 168-173

Technical Note / dx.doi.org/10.13182/NSE83-A17725