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Volume 130

Number 1 | Number 2 | Number 3

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

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

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

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

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

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

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

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

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

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

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

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

Number 2

Experimental Determination and Simulation of the Reactivity Effects and Reaction Rate Sensitivity to Different Ranges of Neutron Energy in Homogeneous Heavy Water Solutions of Thorium

Yu. E. Titarenko, O. V. Shvedov, M. M. Igumnov, E. I. Karpikhin, V. F. Batyaev, A. V. Lopatkin, V. I. Volk, A. Yu. Vakhrushin, S. V. Shepelkov, S. G. Mashnik, T. A. Gabriel

Nuclear Science and Engineering / Volume 130 / Number 2 / October 1998 / Pages 165-180

Technical Paper

Red-Black Response Matrix Acceleration by Transformation of Interface Variables

E. E. Lewis, G. Palmiotti

Nuclear Science and Engineering / Volume 130 / Number 2 / October 1998 / Pages 181-193

Technical Paper

The FN Method for Multigroup Transport Theory with Upscattering

R. D. M. Garcia, C. E. Siewert

Nuclear Science and Engineering / Volume 130 / Number 2 / October 1998 / Pages 194-212

Technical Paper

An Implicit Second-Order Numerical Method for Three-Dimensional Two-Phase Flow Calculations

I. Toumi, D. Caruge

Nuclear Science and Engineering / Volume 130 / Number 2 / October 1998 / Pages 213-225

Technical Paper

Transfer Matrix Treatments in TRIMARAN-II, Nonequally Probable Step Function Representation in Multigroup Monte Carlo

Li Mao, J. P. Both, J. C. Nimal

Nuclear Science and Engineering / Volume 130 / Number 2 / October 1998 / Pages 226-238

Technical Paper

A High-Conversion Water Reactor Design

Y. Ronen, Y. Dali

Nuclear Science and Engineering / Volume 130 / Number 2 / October 1998 / Pages 239-253

Technical Paper

(n,) Reaction Cross Sections of 44Ca, 45Sc, and 51V Nuclei from 13.6 to 14.9 MeV

M. Subasi, M. N. Erduran, M. Bostan, I. A. Reyhancan, E. Gültekin, G. Tarcan, Y. Ozbir, A. Durusoy

Nuclear Science and Engineering / Volume 130 / Number 2 / October 1998 / Pages 254-260

Technical Paper

Improvements in the Theory of Identification of Burst-Shaped Events for Fault Diagnosis

G. Szappanos, G. Por

Nuclear Science and Engineering / Volume 130 / Number 2 / October 1998 / Pages 261-267

Technical Note

Number 3

A Kinetic Theory for Nonanalog Monte Carlo Algorithms: Exponential Transform with Angular Biasing

Taro Ueki, Edward W. Larsen

Nuclear Science and Engineering / Volume 130 / Number 3 / November 1998 / Pages 269-291

Technical Paper

A Probabilistic Method for On-Line Response Prediction of Uncertain and Dynamic Systems

R. B. Vilim

Nuclear Science and Engineering / Volume 130 / Number 3 / November 1998 / Pages 292-308

Technical Paper

The Transmutation of Long-Lived Fission Products by Neutron Irradiation

M. Salvatores, I. Slessarev, A. Tchistiakov

Nuclear Science and Engineering / Volume 130 / Number 3 / November 1998 / Pages 309-319

Technical Paper

Activation by Protons in Range-Thick Lead and Tungsten Spallation Targets

C. E. Laird, D. H. Mullins, D. B. McGibney, John Swartz, R. W. Kamau, C. L. Snead, M. S. Zucker, T. E. Ward, E. M. Franz, G. A. Greene

Nuclear Science and Engineering / Volume 130 / Number 3 / November 1998 / Pages 320-339

Technical Paper

Justification of a Simple Ramsauer Model for Neutron Total Cross Sections

S. M. Grimes, J. D. Anderson, R. W. Bauer, V. A. Madsen

Nuclear Science and Engineering / Volume 130 / Number 3 / November 1998 / Pages 340-347

Technical Paper

Application of a Simple Ramsauer Model for Neutron Total Cross Sections

R. W. Bauer, J. D. Anderson, S. M. Grimes, D. A. Knapp, V. A. Madsen

Nuclear Science and Engineering / Volume 130 / Number 3 / November 1998 / Pages 348-360

Technical Paper

A Computational Fluid Dynamics and Heat Transfer Model for Gaseous Core and Very High Temperature Gas-Cooled Reactors

Samim Anghaie, Gary Chen

Nuclear Science and Engineering / Volume 130 / Number 3 / November 1998 / Pages 361-373

Technical Paper

Monte Carlo Estimates of Transport Solutions to the Isotropic Slab Problem

Thomas E. Booth

Nuclear Science and Engineering / Volume 130 / Number 3 / November 1998 / Pages 374-385

Technical Note

Effect of Low-Energy Resonance Absorber on Positive Neutron Temperature Coefficient of Dilute Plutonium-Water Solution

Toru Obara, Hiroshi Sekimoto

Nuclear Science and Engineering / Volume 130 / Number 3 / November 1998 / Pages 386-390

Technical Note

 
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