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Volume 130

Number 1

The Pencil Beam Problem for Screened Rutherford Scattering

G. C. Pomraning, Anil K. Prinja

Nuclear Science and Engineering / Volume 130 / Number 1 / September 1998 / Pages 1-17

Technical Paper / dx.doi.org/10.13182/NSE98-A1986

Characteristic Methods in Thick Diffusive Problems

Marvin L. Adams, Todd A. Wareing, Wallace F. Walters

Nuclear Science and Engineering / Volume 130 / Number 1 / September 1998 / Pages 18-46

Technical Paper / dx.doi.org/10.13182/NSE98-A1987

Stabilization Techniques for the Nonlinear Analytic Nodal Method

Han Gyu Joo, Guobing Jiang, Thomas J. Downar

Nuclear Science and Engineering / Volume 130 / Number 1 / September 1998 / Pages 47-59

Technical Paper / dx.doi.org/10.13182/NSE98-A1988

A PN Solution to the Multigroup Slowing-Down Problem - I: Basic Formulation

A. D. Caldeira, A. F. Dias, R. D. M. Garcia

Nuclear Science and Engineering / Volume 130 / Number 1 / September 1998 / Pages 60-69

Technical Paper / dx.doi.org/10.13182/NSE98-A1989

A PN Solution to the Multigroup Slowing-Down Problem - II: The Degenerate Case

A. D. Caldeira, A. F. Dias, R. D. M. Garcia

Nuclear Science and Engineering / Volume 130 / Number 1 / September 1998 / Pages 70-78

Technical Paper / dx.doi.org/10.13182/NSE98-A1990

On the Equivalence Between the Discrete Ordinates and the Spherical Harmonics Methods in Radiative Transfer

L. B. Barichello, C. E. Siewert

Nuclear Science and Engineering / Volume 130 / Number 1 / September 1998 / Pages 79-84

Technical Paper / dx.doi.org/10.13182/NSE98-A1991

The Stochastic Behavior of the Eigenvalue Due to Spatial Perturbation in the Fuel Distribution of the One-Speed Slab Reactor

Salim N. Jahshan

Nuclear Science and Engineering / Volume 130 / Number 1 / September 1998 / Pages 85-97

Technical Paper / dx.doi.org/10.13182/NSE98-A1992

Higher Order Generalized Perturbation Theory for Boiling Water Reactor In-Core Fuel Management Optimization

Brian R. Moore, Paul J. Turinsky

Nuclear Science and Engineering / Volume 130 / Number 1 / September 1998 / Pages 98-112

Technical Paper / dx.doi.org/10.13182/NSE98-A1993

On-Line Estimation of Transit Time Using Artificial Neural Networks

T. Tambouratzis, M. Antonopoulos-Domis, M. Marseguerra, E. Padovani

Nuclear Science and Engineering / Volume 130 / Number 1 / September 1998 / Pages 113-127

Technical Paper / dx.doi.org/10.13182/NSE98-A1994

Pressurized Water Reactor Reload Design by an Expert System

Kuan-Jan Lin, Chaung Lin

Nuclear Science and Engineering / Volume 130 / Number 1 / September 1998 / Pages 128-140

Technical Paper / dx.doi.org/10.13182/NSE98-A1995

Passive Neutron Assay of Plutonium Materials: Monte Carlo Procedures to Simulate Generation of Neutron Pulse Trains and the Application of the Neutron Coincidence Counting Method

A. Dodaro, F. V. Frazzoli, R. Remetti

Nuclear Science and Engineering / Volume 130 / Number 1 / September 1998 / Pages 141-152

Technical Paper / dx.doi.org/10.13182/NSE98-A1996

The Central Void Reactivity in the Oak Ridge National Laboratory Enriched Uranium (93.2) Metal Sphere

J. T. Mihalczo, J. J. Lynn, J. R. Taylor

Nuclear Science and Engineering / Volume 130 / Number 1 / September 1998 / Pages 153-163

Technical Paper / dx.doi.org/10.13182/NSE96-121

 
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