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NPRE Undergraduate Seminar Series: Senior Design Presentations

Event Type
Ceremony/Service
Sponsor
Department of Nuclear, Plasma & Radiological Engineering
Location
4039 Campus Instructional Facility (CIF)
Date
Apr 29, 2025   12:00 - 12:50 pm  
Speaker
Dimitri Kalinichenko, Jacob Rice, Sean Siewert & Kenneth Burnett, Bella Pequette, Ceser Zambrano
Contact
Becky Meline
E-Mail
bmeline@illinois.edu
Phone
217-333-3598
Originating Calendar
NPRE Events

NPRE Undergraduate Seminar Series - Spring 2025

 

 

 

 

Senior Design Presentations

 

 

 

 

 

Tuesday, April 29 | 12:00 - 12:50 pm

 

 

 

4039 Campus Instructional Facility (CIF)

 

 

 

 

 

Part of a series of design presentations showcasing the culmination of students' work in capstone course NPRE 458 - Design in NPRE.  Open for all interested students, faculty, and staff to attend.

 

 

 

 

 

Heavy Water Moderated Natural Uranium Microreactor

 

 

 

Dimitri Kalinichenko, Jacob Rice, Sean Siewert

 

 

 

Abstract: Many microreactor designs require the use of high-assay-low-enrichment uranium (HALEU) fuel which is currently not commercially available. Furthermore, the higher enrichment of HALEU fuel imposes additional regulatory requirements, site safety and security risks, and higher costs. To address this barrier to deployment of microreactors, we have designed a thermal spectrum microreactor that operates on naturally enriched uranium fuel with heavy water as a moderator. The design is for a 50 MWth reactor that is transportable via oversize load trucks. The use of natural uranium makes the design feasible for countries that do not have access to enrichment facilities or enriched fuel supplies. The design makes use of annular fuel in order to reduce the parasitic absorption of neutrons by 238U in the fuel, as well as increasing the fuel surface area for improved cooling. Using OpenMC, we have performed depletion simulations and observed an initial multiplicative factor of 1.2 and a fuel lifetime of over a year. Thermalhydraulic simulations have predicted a maximum fuel temperature around 500℃ and have verified sufficient safety margin to prevent boiling and unsafe operating conditions. Economic projections indicate an LCOE of $91.76/MWh, with a projected overnight capital cost of $100-200M. This microreactor design would help accelerate the deployment of microreactor technology and address the unmet need for clean energy in remote locations. 

 

 

 

 

 

Dry Cask Storage Design for Pebble Bed Reactor Spent Fuel

 

 

 

Kenneth Burnett, Bella Pequette, Ceser Zambrano

 

 

 

Abstract: As interest in High-Temperature Gas Reactors (HTGRs), particularly Pebble Bed Reactors (PBRs), grows, there is a need for safe and effective storage solutions for their spent fuel. This senior design project proposes a dry cask storage system tailored to PBR spent fuel pebbles, emphasizing safety, regulatory compliance, and economic feasibility. Our cask will consist of three layers: an outer shell for impact protection, shielding, and an inner cask to hold the fuel. The spent fuel pebbles will be packed in a random configuration with a helium back-fill. Key design challenges — criticality control, graphite oxidation, radiation shielding, and structural stability — are addressed through a Dual-Purpose Cask (DPC) design that will be used for both transport and storage. The dry cask storage unit meets all applicable NRC regulations and follows waste acceptance criteria (WAC) established to site storage casks within the geological repository, Yucca Mountain. In addition to our no-insert design, potential inserts were evaluated for additional stability, heat transfer ability, and neutron absorption. Materials such as borated horizontal spacers and molten metal alloys were assessed, but it was determined that the inserts are not necessary. The inner canister, shielding canister, and outer canister are made of XM-19 stainless steel, DUCRETE, and
304L stainless steel, respectively. OpenMC and LAMMPS were employed to assess neutron behavior, thermal performance, and pebble dynamics. It was found that our cask design remains subcritical (keff <0.95), including under severe accident conditions, and structurally stable. Each cask will hold 17,333 PBR spent pebbles and cost approximately $288,000. Through the development of our design, we determined that a higher fidelity of modeling is required for real-life implementation, but the simple and conservative approach we used was effective for the preliminary design. This design supports the advancement of next generation nuclear waste management systems.

 

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