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Volume 70

Number 3

Table of Contents
Transport Calculations in Cylindrical Geometry(Richard Sanchez)
Physics of High Temperature Reactors(Eberhard Teuchert)
Network Computations Using a Transient Two-Phase Velocity Difference Model(Robert W. Lyczkowski, Delwin C. Mecham, Charles W. Solbrig)
MACK-IV(M. A. Abdou, Y. Gohar, R. Q. Wright)

Two- and Three-Dimensional Neutronics Calculations for the Tokamak Fusion Test Reactor Neutral Beam Injectors

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

Nuclear Science and Engineering / Volume 70 / Number 3 / June 1979 / Pages 225-242

Technical Paper / dx.doi.org/10.13182/NSE79-A20145

Prediction of Statistical Error and Optimization of Biased Monte Carlo Transport Calculations

P. K. Sarkar, M. A. Prasad

Nuclear Science and Engineering / Volume 70 / Number 3 / June 1979 / Pages 243-261

Technical Paper / dx.doi.org/10.13182/NSE79-A20146

Lattice Eigenvalue as a Function of Buckling: Correction to First-Order Perturbation Theory

Ely M. Gelbard, Raymond P. Hughes

Nuclear Science and Engineering / Volume 70 / Number 3 / June 1979 / Pages 262-273

Technical Paper / dx.doi.org/10.13182/NSE79-A20147

Tritium Production in a Sphere of ⁶LiD Irradiated by 14-MeV Neutrons

A. Hemmendinger, C. E. Ragan, Jon M. Wallace

Nuclear Science and Engineering / Volume 70 / Number 3 / June 1979 / Pages 274-280

Technical Paper / dx.doi.org/10.13182/NSE79-A20148

Neutron Interaction with Carbon-12 in the Few-MeV Region

A. Smith, R. Holt, J. Whalen

Nuclear Science and Engineering / Volume 70 / Number 3 / June 1979 / Pages 281-293

Technical Paper / dx.doi.org/10.13182/NSE79-A20149

Neutron Inelastic Scattering in Silicon-28 to 4.15 MeV

N. B. Sullivan, J. J. Egan, G. H. R. Kegel, P. Harihar

Nuclear Science and Engineering / Volume 70 / Number 3 / June 1979 / Pages 294-297

Technical Paper / dx.doi.org/10.13182/NSE79-A20150

Emission Probability of the 312-keV Gamma Ray from the Decay of Protactinium-233

R. J. Gehrke, R. G. Helmer, C. W. Reich

Nuclear Science and Engineering / Volume 70 / Number 3 / June 1979 / Pages 298-306

Technical Paper / dx.doi.org/10.13182/NSE79-A20151

Self-Shielded Fission Rates for Uranium-235

J. B. Czirr

Nuclear Science and Engineering / Volume 70 / Number 3 / June 1979 / Pages 307-308

Technical Note / dx.doi.org/10.13182/NSE79-A20152

Neutron Multiplication Studies in Beryllium for Fusion Reactor Blankets

T. K. Basu, V. R. Nargundkar, P. Cloth, D. Filges, S. Taczanowski

Nuclear Science and Engineering / Volume 70 / Number 3 / June 1979 / Pages 309-313

Technical Note / dx.doi.org/10.13182/NSE79-A20153

Reactor Fuel Burnup Calculations in the LASER Code

Y. Y. Chang, S. K. Loyalka, D. H. Timmons

Nuclear Science and Engineering / Volume 70 / Number 3 / June 1979 / Pages 313-315

Technical Note / dx.doi.org/10.13182/NSE79-A20154

Availability Maximization of Supervised Protective Systems for Nuclear Reactors

J. M. Kontoleon

Nuclear Science and Engineering / Volume 70 / Number 3 / June 1979 / Pages 315-317

Technical Note / dx.doi.org/10.13182/NSE79-A20155

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