American Nuclear Society

/Create an Account

Home

Home / Publications / Journals / Nuclear Science and Engineering / Volume 93 / Number 1

Volume 93

Number 1

Table of Contents
Total Charged-Particle Emission Cross Sections for 9.4- and 11-MeV Neutron Bombardment of Type 316 Stainless Steel(M. Amad, S. L. Graham, S. M. Grimes, H. Satyanarayana, S. K. Saraf, S. Stricklin)

Monte Carlo Simulation of the Gamma Dose Rate in a Loss-of-Water Accident at the North Carolina State University Research Reactor

Joseph M. Doster, Brit E. Hey

Nuclear Science and Engineering / Volume 93 / Number 1 / May 1986 / Pages 1-12

Technical Paper / dx.doi.org/10.13182/NSE83-A17412

One-Dimensional Models for Neutral Particle Transport in Ducts

Edward W. Larsen, Fausto Malvagi, G. C. Pomraning

Nuclear Science and Engineering / Volume 93 / Number 1 / May 1986 / Pages 13-30

Technical Paper / dx.doi.org/10.13182/NSE86-1

Multilevel Analysis of the Low-Energy ²³⁹Pu Cross Sections

R. B. Perez, G. de Saussure, N. M. Larson, R. L. (Roger) Macklin

Nuclear Science and Engineering / Volume 93 / Number 1 / May 1986 / Pages 31-42

Technical Paper / dx.doi.org/10.13182/NSE83-A17414

Capture Cross Sections and Gamma-Ray Spectra from the Interaction of 0.5- to 3.0-MeV Neutrons with Nuclei in the Mass Range A = 63 to 209

J. Voignier, S. Joly, G. Grenier

Nuclear Science and Engineering / Volume 93 / Number 1 / May 1986 / Pages 43-56

Technical Paper / dx.doi.org/10.13182/NSE83-A17415

Experimental Effective Atomic Numbers for the Photoelectric Process in Some Alloys at 84 and 145 keV

K. Siddappa, N. Govinda Nayak, K. M. Balakrishna, N. Lingappa

Nuclear Science and Engineering / Volume 93 / Number 1 / May 1986 / Pages 57-61

Technical Paper / dx.doi.org/10.13182/NSE83-A17416

Vortex Methods for Free Interface Problems

Y. T. Chan, S. Banerjee

Nuclear Science and Engineering / Volume 93 / Number 1 / May 1986 / Pages 62-68

Technical Paper / dx.doi.org/10.13182/NSE83-A17417

Parallel Processing Algorithms for the Finite Difference Solution to the Navier-Stokes Equations

Joseph M. Doster, Matt B. Richards

Nuclear Science and Engineering / Volume 93 / Number 1 / May 1986 / Pages 69-77

Technical Paper / dx.doi.org/10.13182/NSE83-A17418

A Theory of Fuel Management via Backward Diffusion Calculation

Yung-An Chao, Chuan-Wen Hu, Chang-An Suo

Nuclear Science and Engineering / Volume 93 / Number 1 / May 1986 / Pages 78-87

Technical Paper / dx.doi.org/10.13182/NSE83-A17419

Location Analysis for Multiple Gas Tag Releases

F. Schmittroth

Nuclear Science and Engineering / Volume 93 / Number 1 / May 1986 / Pages 88-96

Technical Paper / dx.doi.org/10.13182/NSE83-A17420

Dimensional Analysis of Small-Scale Steam Explosion Experiments

K. Huh, M. L. Corradini

Nuclear Science and Engineering / Volume 93 / Number 1 / May 1986 / Pages 97-104

Technical Note / dx.doi.org/10.13182/NSE83-A17421

Additional Remarks on the Number of Collisions Required to Slow Down a Neutron

Paul Reuss

Nuclear Science and Engineering / Volume 93 / Number 1 / May 1986 / Pages 105-108

Technical Note / dx.doi.org/10.13182/NSE83-A17422

Home|Contact Us|Invoice Payment|Nuclear Links

Privacy Policy|Terms of Use