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Volume 77

Number 3

A Model of Countercurrent Steam-Water Flow in Large Horizontal Pipes

Bart J. Daly, Francis H. Harlow

Nuclear Science and Engineering / Volume 77 / Number 3 / March 1981 / Pages 273-284

Technical Paper / dx.doi.org/10.13182/NSE81-A19838

Sensitivity of Light Water Reactor Fuel Cycle Parameters and Costs to Uncertainties in Thermal Nuclear Data and Methods

J. M. Ryskamp, D. R. Harris, M. Becker

Nuclear Science and Engineering / Volume 77 / Number 3 / March 1981 / Pages 285-296

Technical Paper / dx.doi.org/10.13182/NSE81-A19839

Event Sequences and Consequence Spectrum: A Methodology for Probabilistic Transient Analysis

A. Amendola, G. Reina

Nuclear Science and Engineering / Volume 77 / Number 3 / March 1981 / Pages 297-315

Technical Paper / dx.doi.org/10.13182/NSE81-A19840

Generalized Perturbation Theory for Nonlinear Systems from the Importance Conservation Principle

A. Gandini

Nuclear Science and Engineering / Volume 77 / Number 3 / March 1981 / Pages 316-343

Technical Paper / dx.doi.org/10.13182/NSE81-A19841

A Stability Analysis for Nuclear Reactor Systems

Trine-Yie Dawn

Nuclear Science and Engineering / Volume 77 / Number 3 / March 1981 / Pages 344-351

Technical Note / dx.doi.org/10.13182/NSE81-A19842

Using Orthogonal Functions with a Finite Element Method for Approximating Even-Parity Neutron Flux in Slab Geometry

B. A. Splawski, A. K. Ziver, J. Galliara

Nuclear Science and Engineering / Volume 77 / Number 3 / March 1981 / Pages 351-354

Technical Note / dx.doi.org/10.13182/NSE81-A19843

Stability Analysis for Integro-Differential Coupled-Core Reactor Models

M. Podowski

Nuclear Science and Engineering / Volume 77 / Number 3 / March 1981 / Pages 354-359

Technical Note / dx.doi.org/10.13182/NSE81-A19844

Effectiveness of an Adaptive Acceleration Method for Inner Iterations in Some Neutron Diffusion Codes

Toichiro Fujimura, Yasushi Matsui

Nuclear Science and Engineering / Volume 77 / Number 3 / March 1981 / Pages 360-367

Technical Note / dx.doi.org/10.13182/NSE81-A19845

A Semianalytic Method for the Solution of the Neutron Transport Equation in Plane and Spherical Geometries

J. K. Fletcher

Nuclear Science and Engineering / Volume 77 / Number 3 / March 1981 / Pages 367-372

Technical Note / dx.doi.org/10.13182/NSE81-A19846