ANS / Publications / Journals / Nuclear Science and Engineering

A Technique for Calculation of Continuum Photon and Conversion-Electron Production Cross Sections and Spectra from Neutron-Induced Reactions

S. T. Perkins, R. C. Haight, R. J. Howerton

Nuclear Science and Engineering / Volume 57 / Number 1 / May 1975 / Pages 1-11

Technical Paper / dx.doi.org/10.13182/NSE75-A40337

Total Neutron Cross Section of Hydrogenated Terphenyls for Neutron Energies Between 0.002 and 1.6 eV

H. A. Robitaille, J. S. Hewitt

Nuclear Science and Engineering / Volume 57 / Number 1 / May 1975 / Pages 12-17

Technical Paper / dx.doi.org/10.13182/NSE75-A40338

Fission Cross Section of Uranium-235 from 3 to 20 MeV

J. B. Czirr, G. S. Sidhu

Nuclear Science and Engineering / Volume 57 / Number 1 / May 1975 / Pages 18-27

Technical Paper / dx.doi.org/10.13182/NSE75-A40339

Combined Space-Time Effects of Xenon Transients and Reactor Control During Load Following in a Pebble-Bed High-Temperature Reactor

A. Lauer, W. Fröhling

Nuclear Science and Engineering / Volume 57 / Number 1 / May 1975 / Pages 28-38

Technical Paper / dx.doi.org/10.13182/NSE75-A40340

A Multilevel Approach to Nuclear Fuel Burnup Optimization

W. Ciechanowicz

Nuclear Science and Engineering / Volume 57 / Number 1 / May 1975 / Pages 39-52

Technical Paper / dx.doi.org/10.13182/NSE75-A40341

A New Method for the Numerical Solution of the Two-Dimensional Neutron Diffusion Equation

Katsutada Aoki, Makoto Tsuiki

Nuclear Science and Engineering / Volume 57 / Number 1 / May 1975 / Pages 53-62

Technical Paper / dx.doi.org/10.13182/NSE75-A40342

Thermal-Neutron Transport Processes in Heavy Water in the Temperature Range of 253 to 4 K

G. S. Gangwani, S. P. Tewari, L. S. Kothari

Nuclear Science and Engineering / Volume 57 / Number 1 / May 1975 / Pages 63-74

Technical Paper / dx.doi.org/10.13182/NSE75-A40343

Influence of Deep Minima on Multigroup Cross-Section Generation

Martin Becker

Nuclear Science and Engineering / Volume 57 / Number 1 / May 1975 / Pages 75-77

Technical Note / dx.doi.org/10.13182/NSE75-A40344

Mean-Chord-Length Approximations in the Interface-Currents Formulation of the Collision-Probabilities Techniques

J. M. Sicilian, M. M. Anderson, Jr.

Nuclear Science and Engineering / Volume 57 / Number 1 / May 1975 / Pages 78-81

Technical Note / dx.doi.org/10.13182/NSE75-A40345

On the Treatment of First- and Last-Collision Effects in Neutron Age Theory

Gilbert Epstein, Martin Becker

Nuclear Science and Engineering / Volume 57 / Number 1 / May 1975 / Pages 81-84

Technical Note / dx.doi.org/10.13182/NSE75-A40346

Accurate Extrapolation Lengths for Pulsed Monoenergetic Neutrons in Slabs and Spheres

N. G. Sjöstrand, E. B. Dahl

Nuclear Science and Engineering / Volume 57 / Number 1 / May 1975 / Pages 84-86

Technical Note / dx.doi.org/10.13182/NSE75-A40347

Some Additions to Reactor Noise Theory Which Include Delayed Neutrons

Hsiao-Kang Wang, Lawrence Ruby

Nuclear Science and Engineering / Volume 57 / Number 1 / May 1975 / Pages 86-90

Technical Note / dx.doi.org/10.13182/NSE75-A40348

An Examination of the Capabilities of the Phase Space Time Evolution Method Applied to Neutron Transport

Richard B. Jones, Morton Tavel

Nuclear Science and Engineering / Volume 57 / Number 1 / May 1975 / Pages 90-92

Technical Note / dx.doi.org/10.13182/NSE75-A40349

Use of the Light-Water Neutron Scattering Kernel in the Study of Neutron Transport Processes in Mixtures of Light and Heavy Water

S. P. Tewari

Nuclear Science and Engineering / Volume 57 / Number 1 / May 1975 / Pages 92-93

Technical Note / dx.doi.org/10.13182/NSE75-A40350