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Volume 89

Number 3

Effects of Virtual Mass on the Mathematical Characteristics and Numerical Stability of the Two-Fluid Model

H. C. No, M. S. Kazimi

Nuclear Science and Engineering / Volume 89 / Number 3 / March 1985 / Pages 197-206

Technical Paper / dx.doi.org/10.13182/NSE85-A17541

Scaling Criteria for Nuclear Reactor Thermal Hydraulics

Robert L. Kiang

Nuclear Science and Engineering / Volume 89 / Number 3 / March 1985 / Pages 207-216

Technical Paper / dx.doi.org/10.13182/NSE85-A17542

Effective Buckling Method for Reliable Criticality Calculation of Small Nuclear Systems by Two-Dimensional Diffusion Codes

Yigal S. Gur, Yair Bartal, Shimon Yiftah

Nuclear Science and Engineering / Volume 89 / Number 3 / March 1985 / Pages 217-232

Technical Paper / dx.doi.org/10.13182/NSE85-A17543

Monte Carlo Calculations of the Bremsstrahlung Radiation Environment Expected in the Future Particle Beam Fusion Accelerator Facility PBFA II

M. A. Sweeney, J. N. Olsen

Nuclear Science and Engineering / Volume 89 / Number 3 / March 1985 / Pages 233-246

Technical Paper / dx.doi.org/10.13182/NSE85-A17544

Hadronic Event Generation for Hadron Cascade Calculations and Detector Simulation — Part III: Application of the Model to Hadron Cascade Calculations

H. J. Möhring, J. Ranft

Nuclear Science and Engineering / Volume 89 / Number 3 / March 1985 / Pages 247-255

Technical Paper / dx.doi.org/10.13182/NSE85-A17545

Exact Time-Dependent Moments for the Monoenergetic Neutron Transport Equation with Isotropic Scattering

B. D. Ganapol

Nuclear Science and Engineering / Volume 89 / Number 3 / March 1985 / Pages 256-260

Technical Paper / dx.doi.org/10.13182/NSE85-A17546

An Absolute Measurement of the 7Li(n,n′αt) Reaction Cross Section Between 5 and 14 MeV by Tritium Assaying

M. T. Swinhoe, C. A. Uttley

Nuclear Science and Engineering / Volume 89 / Number 3 / March 1985 / Pages 261-272

Technical Paper / dx.doi.org/10.13182/NSE85-A17547

A Neutron Buildup Determination and Its Properties

D. R. Wyman, A. A. Harms

Nuclear Science and Engineering / Volume 89 / Number 3 / March 1985 / Pages 273-279

Technical Note / dx.doi.org/10.13182/NSE85-A17548

Statistical Estimates of Thermal Neutron Capture Cross Sections

Yu. V. Petrov, A. I. Shlyakhter

Nuclear Science and Engineering / Volume 89 / Number 3 / March 1985 / Pages 280-281

Technical Note / dx.doi.org/10.13182/NSE85-A17549

An Efficient Algorithm for Nodal-Transport Solutions in Multidimensional Geometry

Ahmed Badruzzaman

Nuclear Science and Engineering / Volume 89 / Number 3 / March 1985 / Pages 281-290

Technical Note / dx.doi.org/10.13182/NSE85-A17550