The Density and Compressibility of Liquid (U,Pu)-Mixed Oxide
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
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
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
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
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
Nuclear Science and Engineering / Volume 105 / Number 3 / July 1990 / Pages 271-277
Technical Paper / dx.doi.org/10.13182/NSE90-A19191
Nuclear Science and Engineering / Volume 105 / Number 3 / July 1990 / Pages 278-289
Technical Paper / dx.doi.org/10.13182/NSE90-A19192
Nuclear Science and Engineering / Volume 105 / Number 3 / July 1990 / Pages 290-296
Technical Notes / dx.doi.org/10.13182/NSE90-A19193
Nuclear Science and Engineering / Volume 105 / Number 3 / July 1990 / Pages 297-299
Technical Notes / dx.doi.org/10.13182/NSE90-A19194