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Volume 85

Number 3

Transient Two-Phase Two-Component Water-Steam-Air Flow

N. I. Kolev

Nuclear Science and Engineering / Volume 85 / Number 3 / November 1983 / Pages 209-220

Technical Paper / dx.doi.org/10.13182/NSE83-A17313

The Transport of Radioactive Corrosion Products in High-Temperature Water—III. The Interaction of Dissolved Cobalt with Heated Surfaces

D. H. Lister, S. A. Kushneriuk, R. H. Campbell

Nuclear Science and Engineering / Volume 85 / Number 3 / November 1983 / Pages 221-232

Technical Paper / dx.doi.org/10.13182/NSE83-A17314

On the Theory of Transport of Fluids in Fractured Media for the Safety Analysis of a Nuclear Waste Repository

Nimai C. Mukhopadhyay

Nuclear Science and Engineering / Volume 85 / Number 3 / November 1983 / Pages 233-244

Technical Paper / dx.doi.org/10.13182/NSE83-A17315

Calibration of Self-Powered Neutron Detectors

M. F. Sulcoski, H. D. Warren

Nuclear Science and Engineering / Volume 85 / Number 3 / November 1983 / Pages 245-250

Technical Paper / dx.doi.org/10.13182/NSE83-A17316

Neutron Capture and Fission Cross Section of 243Am in the Energy Range from 5 to 250 keV

K. Wisshak, F. Käppeler

Nuclear Science and Engineering / Volume 85 / Number 3 / November 1983 / Pages 251-260

Technical Paper / dx.doi.org/10.13182/NSE83-A17317

The Total Neutron Cross Sections of 249Bk and 249Cf Below 100 eV

Richard W. Benjamin, John A. Harvey, Nathaniel W. Hill, Madhu S. Pandey, Robert F. Carlton

Nuclear Science and Engineering / Volume 85 / Number 3 / November 1983 / Pages 261-270

Technical Paper / dx.doi.org/10.13182/NSE83-A17318

The Fission Cross Section of 237Np Relative to 235U from 0.1 to 9.4 MeV

J. W. Meadows

Nuclear Science and Engineering / Volume 85 / Number 3 / November 1983 / Pages 271-279

Technical Paper / dx.doi.org/10.13182/NSE83-A17319

Measurements of Fast Neutron Number Albedos for Double-Layered Slabs

Kazuo Shin, Hiroyuki Nakano, Tomonori Hyodo

Nuclear Science and Engineering / Volume 85 / Number 3 / November 1983 / Pages 280-288

Technical Paper / dx.doi.org/10.13182/NSE83-A17320

The Finite Element Response Matrix Method

Horacio Nakata, William R. Martin

Nuclear Science and Engineering / Volume 85 / Number 3 / November 1983 / Pages 289-305

Technical Paper / dx.doi.org/10.13182/NSE83-A17321

Multigroup Transfer Matrices for Charged-Particle and Neutron-Induced Reactions—Part III: Energy Conservation and Local Deposition

S. T. Perkins, R. J. Howerton

Nuclear Science and Engineering / Volume 85 / Number 3 / November 1983 / Pages 306-313

Technical Paper / dx.doi.org/10.13182/NSE83-A17322

Measurement of the Subthreshold Neutron-Induced Fission Cross Section of 240Pu Relative to 235U from 5 to 300 keV

J. W. Behrens

Nuclear Science and Engineering / Volume 85 / Number 3 / November 1983 / Pages 314-318

Technical Note / dx.doi.org/10.13182/NSE83-A17323