"This thesis presents both an experimental and analytical analysis of the scram characteristics of a fluid control system for a nuclear reactor. This control system utilizes a control tube containing a neutron-absorbing fluid. The level of the fluid inside of the tube is then regulated by means of' a pressurized gas and offers a number of unique advantages over the conventional control rod system using linear absorber rods.
The effect of varying the level-control pressure and initial height of the fluid column is determined and evaluated. The time required to complete a scram with the fluid control system is compared to the rod drop times of an operating reactor.
The dynamic response of the liquid control system during scram was found to be as fast or faster than a linear-control-rod system of an operating reactor"--Abstract, page iii.
Culp, Archie W., Jr.
Edwards, Charles L., 1934-
Gillett, Billy E.
Bolon, Albert E., 1939-2006
Mechanical and Aerospace Engineering
M.S. in Mechanical Engineering
University of Missouri at Rolla
xii, 58 pages
© 1966 Roger Alan Crane, All rights reserved.
Thesis - Open Access
Library of Congress Subject Headings
Nuclear reactors -- Fluid dynamics
Electric resistance -- Measurement
Nuclear fuel rods
Print OCLC #
Electronic OCLC #
Link to Catalog Record
Crane, Roger Alan, "A fluid control system for nuclear reactors" (1966). Masters Theses. 4181.