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  5. High-Temperature Gas-Cooled Microreactors in Continuous Recycle Nuclear Fuel Cycles for Reducing Nuclear Waste and Environmental Impact
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High-Temperature Gas-Cooled Microreactors in Continuous Recycle Nuclear Fuel Cycles for Reducing Nuclear Waste and Environmental Impact

Date Issued
May 1, 2025
Author(s)
Vallabhaneni, Venkata S  
Advisor(s)
Nicholas R. Brown
Additional Advisor(s)
Nicholas R. Brown
Ivan Maldonado
Sandra Bogetic
Permanent URI
https://trace.tennessee.edu/handle/20.500.14382/35496
Abstract

This work adapts both prismatic and pebble-bed micro high-temperature gas-cooled reactor (HTGR) point designs for Pu/TRU driver fuel under a continuous recycle fuel cycle. The adapted prismatic and pebble-bed micro-HTGR point designs are optimized to maximize fuel discharge burnup to reduce waste disposed, fuel cycle costs, and environmental impact. Optimization was performed for inert matrix fuel (IMF) concepts using different composite moderators in prismatic and pebble-bed designs. The prismatic and pebble-bed designs use (TRU) oxide tristructural-isotropic (TRISO) fuel. Moderator material includes beryllium (Be), beryllium oxide (BeO), yttrium hydride (YHx=1.9), or zirconium hydride (ZrHx=1.6) entrained in a MgO host matrix. For each prismatic IMF concept, optimization studies were performed to maximize discharge burnup by varying the TRISO packing fraction and assembly lattice pitch. For each pebble-bed IMF concept, optimization studies were performed by varying the TRISO packing fraction, the pebble fueled radius, the ratio of fueled to unfueled pebbles, and the active reactor core radius. Energy-normalized metrics for the mass of spent nuclear fuel and high-level waste (SNF&HLW) disposed, volume of low-level waste (LLW) disposed, metric tons of natural uranium (MTNU) used, area of land used, volume of water used, mass of carbon dioxide (CO2) produced, and activity of SNF&HLW at 100 and 100,000 years are calculated for the continuous recycle prismatic and pebble-bed IMF concepts. These metric results are compared to those of a graphite reference design, once-through prismatic and pebble-bed IMF concepts, a light water reactor (LWR), and a small modular reactor (SMR). All continuous recycle IMF concepts outperformed the graphite reference case for all evaluated metrics. Additionally, all continuous recycle IMF concepts outperformed their once-through counterparts, the LWR, and SMR for nearly all evaluated metrics. For the mass of SNF&HLW disposed, the continuous recycle designs saw a 92.7% reduction. For the volume of LLW disposed, the continuous recycle designs saw between 29.7% to 31.1% reduction. Overall, the continuous recycle IMF concepts significantly reduced waste disposed, fuel cycle cost, and environmental impact compared to conventional once-through designs.

Subjects

Microreactor

HTGR

TRU

Fuel Cycle

Recycle

Composite Moderator

Disciplines
Nuclear Engineering
Degree
Master of Science
Major
Nuclear Engineering
Embargo Date
May 15, 2026
File(s)
Thumbnail Image
Name

Revised_Thesis.docx

Size

14.41 MB

Format

Microsoft Word XML

Checksum (MD5)

e027671ca87ca70bcd519bd813c1a4ea

Thumbnail Image
Name

auto_convert.pdf

Size

5.54 MB

Format

Adobe PDF

Checksum (MD5)

6b6db7f291304ef8b7eab4287ef892c9


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