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Volume 105

Number 3

The Density and Compressibility of Liquid (U,Pu)-Mixed Oxide

W. Breitung, K. O. Reil

Nuclear Science and Engineering / Volume 105 / Number 3 / July 1990 / Pages 205-217

Technical Paper / dx.doi.org/10.13182/NSE90-A19186

Neutron Kinetics Investigations at the LR-0 Zero-Power Reactor

V. Rypar, J. Racek, K.-H. Fährmann, U. Grundmann, D. Ziegenbein

Nuclear Science and Engineering / Volume 105 / Number 3 / July 1990 / Pages 218-232

Technical Paper / dx.doi.org/10.13182/NSE90-A19187

Gamma-Ray Activation and Passive Neutron Methods for Nondestructive Assay of Spent-Fuel Assemblies

Zs. Németh, Á. Veres, I. Pavlicsek, L. Lakosi

Nuclear Science and Engineering / Volume 105 / Number 3 / July 1990 / Pages 233-243

Technical Paper / dx.doi.org/10.13182/NSE90-A19188

Analysis of Sample and Fuel Pin Irradiation Experiments in Phénix for Basic Nuclear Data Validation

A. D’Angelo, F. Cleri, P. Marimbeau, M. Salvatores, J. P. Grouiller

Nuclear Science and Engineering / Volume 105 / Number 3 / July 1990 / Pages 244-255

Technical Paper / dx.doi.org/10.13182/NSE90-A19189

Variational Formulation of a Higher Order Nodal Diffusion Method

D. V. Altiparmakov, Dj. Tomašević

Nuclear Science and Engineering / Volume 105 / Number 3 / July 1990 / Pages 256-270

Technical Paper / dx.doi.org/10.13182/NSE90-A19190

Wiener-Hopf Technique Solution to a Rewetting Model with Precursory Cooling

Shmuel Olek

Nuclear Science and Engineering / Volume 105 / Number 3 / July 1990 / Pages 271-277

Technical Paper / dx.doi.org/10.13182/NSE90-A19191

Comparison of Calculated Results with Experimental Data for the Tritium Production Rates in a Li2O Assembly

R. T. Santoro, R. G. Alsmiller, Jr., J. M. Barnes, T. A. Gabriel

Nuclear Science and Engineering / Volume 105 / Number 3 / July 1990 / Pages 278-289

Technical Paper / dx.doi.org/10.13182/NSE90-A19192

A Generalized Perturbation Theory for the Reconstruction of the Axial Offset in a Pressurized Water Reactor

G. B. Bruna, R. Aigle, O. Loussouarn

Nuclear Science and Engineering / Volume 105 / Number 3 / July 1990 / Pages 290-296

Technical Notes / dx.doi.org/10.13182/NSE90-A19193

Simultaneous Estimation of Neutron Density and Reactivity in a Nuclear Reactor Using a Bank of Kalman Filters

Carlos E. D’Attellis, Elsa Cortina

Nuclear Science and Engineering / Volume 105 / Number 3 / July 1990 / Pages 297-299

Technical Notes / dx.doi.org/10.13182/NSE90-A19194