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Volume 111

Number 2

An Extension of the Rigorous Pole Representation of Cross Sections for Reactor Applications

Richard N. Hwang

Nuclear Science and Engineering / Volume 111 / Number 2 / June 1992 / Pages 113-131

Technical Paper / dx.doi.org/10.13182/NSE92-A23928

The Interaction of 1- to 20-MeV Neutrons with 238U

A. C. Merchant, P. E. Hodgson, H. R. Schelin

Nuclear Science and Engineering / Volume 111 / Number 2 / June 1992 / Pages 132-144

Technical Paper / dx.doi.org/10.13182/NSE92-A23929

Diffusion Synthetic Acceleration of Discontinuous Finite Element Transport Iterations

Marvin L. Adams, William R. Martin

Nuclear Science and Engineering / Volume 111 / Number 2 / June 1992 / Pages 145-167

Technical Paper / dx.doi.org/10.13182/NSE92-A23930

Three-Dimensional Variational Nodal Transport Methods for Cartesian, Triangular, and Hexagonal Criticality Calculations

C. B. Carrico, E. E. Lewis, G. Palmiotti

Nuclear Science and Engineering / Volume 111 / Number 2 / June 1992 / Pages 168-179

Technical Paper / dx.doi.org/10.13182/NSE92-1

Domain Decomposition of a Two-Dimensional Sn Method

Ronald Mattis, Alireza Haghighat

Nuclear Science and Engineering / Volume 111 / Number 2 / June 1992 / Pages 180-196

Technical Paper / dx.doi.org/10.13182/NSE92-A23932

Influence of Delayed Neutron Spectra on Fast Reactor Criticality

Edgar Kiefhaber

Nuclear Science and Engineering / Volume 111 / Number 2 / June 1992 / Pages 197-204

Technical Note / dx.doi.org/10.13182/NSE92-A23933

Sensitivity Theory for the Closed Nuclear Fuel Cycle

H. B. Choi, T. J. Downar

Nuclear Science and Engineering / Volume 111 / Number 2 / June 1992 / Pages 205-213

Technical Note / dx.doi.org/10.13182/NSE92-A23934