Nuclear Engineering ETDs

Publication Date

12-12-1969

Abstract

The initial-value problem for the transport of monoenergetic neutrons in slab geometry with delayed neutron production is studied using numerical methods based on the analysis of Kaper. The eigenvalues and eigenfunctions of the transport operator are found by numerical solution of the equations which result from application of the normal mode expansion method. The residual terms in this form of the solution of the initial-value problem are evaluated by direct numerical integrations on the (complex) resolvent set of the transport operator. The results obtained in this study are compared with the results from the method of matched asymptotic expansions.

Sponsors

The Atomic Energy Commission through its Special Fellowship Program in Nuclear Science and Engineering and its Associated Western Universities Fellowship Program

Document Type

Dissertation

Language

English

Degree Name

Nuclear Engineering

Level of Degree

Doctoral

Department Name

Nuclear Engineering

First Committee Member (Chair)

Ralph Douglas O'Dell

Second Committee Member

William L. Hendry

Third Committee Member

Robert Leroy Long

Fourth Committee Member

Glenn Alan Whan

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