Thermal-hydraulic optimization for high production of low-enriched uranium based molybdenum-99

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Thermal-hydraulic optimization for high production of low-enriched uranium based molybdenum-99

Please use this identifier to cite or link to this item: http://hdl.handle.net/10355/6538

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Title: Thermal-hydraulic optimization for high production of low-enriched uranium based molybdenum-99
Author: Scott, Jeff (Jeffrey William)
Date: 2009
Publisher: University of Missouri--Columbia
Abstract: Globally, more than 20 million samples of technetium-99 are used annually to diagnose many different forms of cancer. Despite this, there are only four main nuclear reactors worldwide that produce molybdenum-99, the parent isotope of technetium-99m. In an attempt to address the growing demand, as well as to motivate the current reactors to stop using high-enriched uranium, the University of Missouri Research Reactor (MURR) has begun to produce molybdenum-99 using low-enriched uranium. The fission of uranium-235, for which one of the products is molybdenum-99, generates approximately 2 kW of heat per 4-gram target. Continually removing this heat from the fission reaction is the limiting factor in the high-volume production process. The objective of this thesis is to find a reactor wedge setup with maximum rate of heat removal, thereby maximizing the amount of molybdenum-99 that can be created in the reactor. To maximize heat transfer, a quasi 1-D analytic model, calibrated numerically, is created to hydraulically and thermally model the coolant flow through the current reactor setup. Using flow network modeling (FNM), this analytic model is expanded to analyze other potential geometries that could maximize heat transfer. The findings show that for a single channel under the existing reactor configuration, a maximum of 19.18 kW can be dispersed. By opening the drain and slightly shrinking the channel diameter, this can be improved to 22.77 kW. When the system is expanded to 10 parallel channels and the drain is fully opened, over 250 kW can theoretically be achieved, though the neutronics of the MURR reactor will likely limit this.
URI: http://hdl.handle.net/10355/6538
Other Identifiers: ScottJ-051909-T981

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