Abstract
This work expands on a pre-conceptual microreactor design based on a High Temperature Gas-Cooled Reactor (HTGR) platform generated in the companion paper of this study. Here, power, coolant inlet temperature, and coolant outlet temperature are varied to outline an operable design space associated maximum allowable component temperatures and coolant pressure drop for a given microreactor design. Calculations show that beryllium- and hydride-based composite moderators have a smaller operating design space than graphite because of a lower allowable moderator temperature under the conservative upper limits employed for this study. Power below 6MWth was considered to be undesirable for all designs because of a limited inlet/outlet temperature range. Reactivity Temperature Coefficients (RTC) are calculated to illustrate an inherent safety feature of HTGRs and are fed into a Depressurized Loss of Forced Coolant (DLOFC) without active intervention accident simulation, considered to be a bounding case for fuel temperatures in a HTGR. RTC calculations showed that all designs would expect to have a negative isothermal coefficient through their entire operating cycle and DLOFC calculations showed no case exceed their maximum temperature limits. An additional accident that simulates the release of fission products is performed to compare expected minimum Emergency Planning Zone (EPZ) size for all designs.
Original language | English |
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Article number | 104258 |
Journal | Progress in Nuclear Energy |
Volume | 149 |
DOIs | |
State | Published - Jul 2022 |
Externally published | Yes |
Funding
The authors would like to thank Robert F. Kile of the University of Tennessee, Knoxville for his assistance and guidance with the thermal-hydraulics model. The authors would also like to thank Dr. Bin Cheng of Stony Brook University and Dr. Xunxiang Hu of Oak Ridge National Laboratory for their insightful discussions on the thermophysical properties of the composite moderators. The authors would also like to extend their gratitude to Dr. Gerhard Strydom and Dr. Aaron Epiney for providing the RELAP models for the INL HTGTR. This work was funded by the Advanced Research Projects Agency-Energy (ARPA-E) program: Modeling-Enhanced Innovations Trailblazing Nuclear Energy Reinvigoration (MEITNER) under contract DE-AR0000977. This work was funded by the Advanced Research Projects Agency-Energy (ARPA-E) program: Modeling-Enhanced Innovations Trailblazing Nuclear Energy Reinvigoration (MEITNER) under contract DE-AR0000977 .
Funders | Funder number |
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Modeling-Enhanced Innovations Trailblazing Nuclear Energy Reinvigoration | DE-AR0000977 |
Advanced Research Projects Agency - Energy | |
University of Tennessee |
Keywords
- Beryllium
- HTGR
- Hydride
- Microreactor