As many of you know, I have been a part-time graduate student at the University of Tennessee for several years now. Since I live in Alabama, I take classes online in pursuit of my masters' degree in nuclear engineering. I'm about 3/4 of the way through my degree, but with three kids and a full-time job, it's pretty slow-going.
This semester, I took the second course in UT's graduate level reactor design sequence and I had the opportunity to work with a team of other students in a similar situation. My team members were Bill Casino and Chris Whitener, who are practicing nuclear engineers who also are working on their masters' degrees part-time through the UT distance learning program.
This class began in January, and we were assigned a reactor design problem. Here is the problem statement:
Quote:
Small Mobile Reactor for Underdeveloped Countries and Remote Locations
The objective of this project is to design a small reactor that can be transported by truck to a remote location. In addition to its small size, it will not be refueled on site but rather will be removed by truck and replaced with a reactor with a fresh core. Although the capacity remains to be chosen, 100 MW electric is a reasonable goal.
This project has considerable latitude it its design. Weight and size will probably make a pressure vessel impractical. However, a CANDU type design might be used with water as a coolant. Selection of the coolant will be a major design task left wide open. Liquid metals, gas, molten salt, or water will all be considered. The secondary plant must also be considered. However, the entire plant need not be delivered on a single truck; it might take several truck loads with a single load for the reactor at the time of refueling.
The reactor need not be thermal. We will also consider the advantages of a fast spectrum reactor using a liquid metal coolant.
Elements of Design
1. Power Coefficient and Void Coefficient
Both of these coefficients are of utmost importance for operation and safety. Since most of our experience is with water reactors, consideration of other coolants will introduce us to a new regime. Fast reactors will also bring us into a new area. In all cases, we must have a negative void coefficient and a negative power coefficient.
2. Neutron transport
This area will be important in evaluating the longevity of the fuel cycle, the power and void coefficients, and the flux profile. The small size is expected to aid in reactor control. The core geometry may be adjusted to optimize power coefficient and flux shape.
3. Heat Transfer
Thermal hydraulics will be considered not only for steady state heat removal but for decay heat removal upon shutdown or accident conditions. Many designs are available that enable natural circulation cooling under accident conditions. This will also be a consideration in our reactor.
4. Materials Selection
High temperature and high efficiency are not prime considerations. However, the more efficient, the smaller the reactor can be made. We must select materials that will withstand operating temperatures and the long fuel cycle. However, this is not a research project, only a conceptual design. We will identify areas for future research on materials or other requirements.
5. Secondary System
The secondary system will not be an area on which we will focus. However, we must identify the type of system and have an estimate of its size. Steam generators are very large. Perhaps another system will be more favorable.
6. Safety
Safety is always a consideration in a design project. For a remote reactor, it is a goal for it to operate with a minimum of intervention. Convection cooling in case of pump failure is a major advantage. Containment is essential. However, this will not be a major part of the design effort. Concepts that are already established can be used.
To this end, we considered several different reactor options, ultimately settling on a liquid-fluoride reactor with a helium gas turbine power conversion system. Because of restrictions on the uranium enrichment of the fuel, I made the decision not to use thorium in the salt, instead opting for a "once-through" fuel cycle not terribly dissimilar from today's light-water reactors in terms of fuel consumption.
However, the capability exists to design a different core, with fuel and blanket loops and more sophisticated reprocessing, that could actually burn thorium instead of U-235. Whether or not that capability would mesh with the proliferation resistance and remote deployment requirements is still a valid subject of debate.
At any rate, for your enjoyment, here is our final report and the presentation I gave at the university on April 25th.
Paper (3.2 MB)
Presentation (2.7 MB)
If you wish to reference this work, please link to this discussion thread rather than to the paper or presentation themselves so that readers can get some of the background of the study.
My team worked very very hard to put this together and I want them to know how much I appreciate their efforts. Your comments are appreciated as well.