American Nuclear Society
Home

Home / Publications / Journals / Nuclear Science and Engineering / Volume 161 / Number 1 / Pages 49-67

An Analytical Approximation Solution for a Time-Dependent Neutron Transport Problem with External Source and Delayed Neutron Production

B. Merk

Nuclear Science and Engineering / Volume 161 / Number 1 / January 2009 / Pages 49-67

Technical Paper

This work presents the development of an analytical approximation solution for a space-time-dependent neutron transport problem in a one-dimensional system consisting of a homogenized medium with a central external source with Green's functions. The delayed neutron production is implemented with the multiple-scale expansion method. Qualitative results for a given system are analyzed and an example of the use for the analysis of accelerator-driven systems is given.

 
Questions or comments about the site? Contact the ANS Webmaster.
advertisement