"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.
Bolon, Albert E., 1939-2006
Mining and Nuclear Engineering
M.S. in Nuclear Engineering
University of Missouri--Rolla
xi, 171 pages
© 1986 Omar Ivan Aguilar, All rights reserved.
Thesis - Open Access
Print OCLC #
Link to Catalog Record
Aguilar, Omar Ivan, "Fuel loading for a low-leakage core in a pressurized water reactor" (1986). Masters Theses. 390.