Masters Theses

Abstract

"A study of low-leakage core fuel loading as a means to reduce fast neutron flux incident upon the pressure vessel is presented. The specific case under study is Cycle 5 of Arkansas Nuclear One - Unit Two (ANO-2), a Combustion Engineering Pressurized Water Reactor. Neutron transport calculations were performed using the DOT two-dimensional transport code. The results from DOT provide the angular distribution of the fast neutron flux at the surface of the pressure vessel.

Seven different fuel loading schemes were studied and compared to the Reference Case. The angular distribution of the fast neutron flux for all cases studied showed the occurrence of two different flux peaks. Six of the seven fuel loading schemes studied resulted in reductions of the fast neutron flux at the surface of the pressure vessel. Fast flux reductions ranged from 0.1% to 47% in one of the flux peaks, while reductions from 12.9% to 45.8% were accomplished in the other peak. Total fast flux reductions ranged from 11.7% to 45.3%. Low-leakage core fuel loading proved to be a flexible fast flux reduction alternative"--Abstract, page ii.

Advisor(s)

Tsoulfanidis, Nicholas

Committee Member(s)

Bolon, Albert E., 1939-2006
Brooks, William

Department(s)

Mining and Nuclear Engineering

Degree Name

M.S. in Nuclear Engineering

Publisher

University of Missouri--Rolla

Publication Date

Summer 1986

Pagination

xi, 171 pages

Note about bibliography

Includes bibliographical references (pages 114-118).

Rights

© 1986 Omar Ivan Aguilar, All rights reserved.

Document Type

Thesis - Open Access

File Type

text

Language

English

Thesis Number

T 5370

Print OCLC #

14707534

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