Home / Publications / Journals / Nuclear Science and Engineering / Volume 50 / Number 1

Volume 50

Number 1

Table of Contents
A Program for Calculating Thermal Neutron Scattering Kernels(A. G. Gibbs, C. W. Lindenmeier)
Nuclear Radiation Physics(Newton Underwood)
Education and Research in the Nuclear Fuel Cycle(C. E. Stevenson)

Two-Group Critical Problems for Slabs and Spheres in Neutron-Transport Theory

J. T. Kriese, C. E. Siewert, Y. Yener

Nuclear Science and Engineering / Volume 50 / Number 1 / January 1973 / Pages 3-9

Technical Paper / dx.doi.org/10.13182/NSE73-A22582

Neutron Transport for a Slab with a Degenerate Scattering Kernel

H. A. Larson, N. J. McCormick

Nuclear Science and Engineering / Volume 50 / Number 1 / January 1973 / Pages 10-19

Technical Paper / dx.doi.org/10.13182/NSE73-A22583

Improved Moment Method Calculations of Gamma-Ray Transport: Application to Point Isotropic Sources in Water

L. V. Spencer, G. L. Simmons

Nuclear Science and Engineering / Volume 50 / Number 1 / January 1973 / Pages 20-31

Technical Paper / dx.doi.org/10.13182/NSE73-A22584

Moments Method Calculation of Buildup Factors for Point Isotropic Monoenergetic Gamma-Ray Sources at Depths Greater than 20 Mean-Free-Paths

E. E. Morris

Nuclear Science and Engineering / Volume 50 / Number 1 / January 1973 / Pages 32-37

Technical Paper / dx.doi.org/10.13182/NSE73-A22585

A Pulsed Neutron Experiment with Beryllium by the Use of a Gamma-Ray Flash from an Electron Linear Accelerator

Otohiko Aizawa, Hiroyuki Kadotani, Keiji Kanda, Yoshiaki Fujita

Nuclear Science and Engineering / Volume 50 / Number 1 / January 1973 / Pages 38-45

Technical Paper / dx.doi.org/10.13182/NSE73-A22586

On the Use of Maximum Principle in Optimal Xenon Shutdown Problems

Seppo Salo

Nuclear Science and Engineering / Volume 50 / Number 1 / January 1973 / Pages 46-52

Technical Paper / dx.doi.org/10.13182/NSE73-A22587

Analysis of the Coolant Behavior Following Fuel Failure and Molten Fuel-Sodium Interaction in a Fast Nuclear Reactor

A. W. Cronenberg, H. K. Fauske, D. T. Eggen

Nuclear Science and Engineering / Volume 50 / Number 1 / January 1973 / Pages 53-62

Technical Paper / dx.doi.org/10.13182/NSE73-A22588

Sensitivity Analysis of Ideal Centrifuge Cascade for Producing Slightly Enriched Uranium

Toshio Kawai, Kotaro Inoue, Hiroshi Motoda, Tomofumi Kobayashi, Takashi Kiguchi

Nuclear Science and Engineering / Volume 50 / Number 1 / January 1973 / Pages 63-72

Technical Paper / dx.doi.org/10.13182/NSE73-A22589

Monte Carlo Confidence Limits for Iterated-Source Calculations

D. B. MacMillan

Nuclear Science and Engineering / Volume 50 / Number 1 / January 1973 / Pages 73-75

Technical Note / dx.doi.org/10.13182/NSE73-A22590

Studies in Spectral Neutron Flux Synthesis

Harold Greenspan

Nuclear Science and Engineering / Volume 50 / Number 1 / January 1973 / Pages 75-78

Technical Note / dx.doi.org/10.13182/NSE73-A22591

The Effective Cross Section for the ¹⁶O(d, n)¹⁷ F Reaction for Fission Neutrons Moderated by Heavy Water

H. S. Pruys, B. D. Ganapol

Nuclear Science and Engineering / Volume 50 / Number 1 / January 1973 / Pages 79-80

Technical Note / dx.doi.org/10.13182/NSE73-A22592

Revised Delayed-Neutron Yield Data

A. E. Evans, M. M. Thorpe, M. S. Krick

Nuclear Science and Engineering / Volume 50 / Number 1 / January 1973 / Pages 80-82

Technical Note / dx.doi.org/10.13182/NSE73-A22593

Merit Index for Gas-Cooled Reactor Heat Transfer

G. Melese-d’Hospital

Nuclear Science and Engineering / Volume 50 / Number 1 / January 1973 / Pages 83-85

Technical Note / dx.doi.org/10.13182/NSE73-A22594

Thermal Characterization of Restructured Fuel

Aaron J. Friedland

Nuclear Science and Engineering / Volume 50 / Number 1 / January 1973 / Pages 85-87

Technical Note / dx.doi.org/10.13182/NSE73-A22595