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Volume 111

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Nuclear Science and Engineering / Volume 111 / Number 4

August 1992

Table of Contents

Nuclear Science and Engineering / Volume 111 / Number 1

May 1992

Table of Contents

Nuclear Science and Engineering / Volume 111 / Number 2

June 1992

Table of Contents

Nuclear Science and Engineering / Volume 111 / Number 3

July 1992

Canada Deuterium Uranium Reactor Design Optimization Using Three-Dimensional Generalized Perturbation Theory

D. Rozon, M. Beaudet

Nuclear Science and Engineering / Volume 111 / Number 1 / Pages 1-20

May 1992

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Reconstruction of Pin Power and Burnup Characteristics from Nodal Calculations in Hexagonal-Z Geometry

W. S. Yang, P. J. Finck, H. Khalil

Nuclear Science and Engineering / Volume 111 / Number 1 / Pages 21-33

May 1992

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A Spectral Nodal Method for One-Group X,Y-Geometry Discrete Ordinates Problems

Ricardo C. De Barros, Edward W. Larsen

Nuclear Science and Engineering / Volume 111 / Number 1 / Pages 34-45

May 1992

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A Massively Parallel Discrete Ordinates Response Matrix Method for Neutron Transport

U. R. Hanebutte, E. E. Lewis

Nuclear Science and Engineering / Volume 111 / Number 1 / Pages 46-56

May 1992

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An Iterative Algorithm for Solving the Multidimensional Neutron Diffusion Nodal Method Equations on Parallel Computers

Bernadette L. Kirk, Yousry Y. Azmy

Nuclear Science and Engineering / Volume 111 / Number 1 / Pages 57-65

May 1992

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Estimation of Neutron Flux and Xenon Distributions via Observer-Based Control Theory

Young Ho Park, Nam Zin Cho

Nuclear Science and Engineering / Volume 111 / Number 1 / Pages 66-81

May 1992

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Ex-Vessel Releases of Radionuclides During Molten Core/Concrete Interactions in Severe Light Water Reactor Accidents

Min Lee, Jan Sea Wu

Nuclear Science and Engineering / Volume 111 / Number 1 / Pages 82-101

May 1992

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Time-Dependent Monte Carlo Calculations of the Oak Ridge Electron Linear Accelerator Target Neutron Spectrum

S. N. Cramer, F. G. Perey

Nuclear Science and Engineering / Volume 111 / Number 1 / Pages 102-111

May 1992

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

Richard N. Hwang

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

June 1992

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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 / Pages 132-144

June 1992

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Diffusion Synthetic Acceleration of Discontinuous Finite Element Transport Iterations

Marvin L. Adams, William R. Martin

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

June 1992

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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 / Pages 168-179

June 1992

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Domain Decomposition of a Two-Dimensional Sn Method

Ronald Mattis, Alireza Haghighat

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

June 1992

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Influence of Delayed Neutron Spectra on Fast Reactor Criticality

Edgar Kiefhaber

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

June 1992

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Sensitivity Theory for the Closed Nuclear Fuel Cycle

H. B. Choi, T. J. Downar

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

June 1992

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A Comparison of Models for Particle Transport Through Stochastic Mixtures

F.Malvagi, G. C. Pomraning

Nuclear Science and Engineering / Volume 111 / Number 3 / Pages 215-228

July 1992

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