Abstract
We conducted reactor performance calculations to assess the potential design basis accident performance of HTGR fuel designs. Three Fully Ceramic Microencapsulated (FCM) fueled HTGR designs were developed in a previous work (Lu et al., 2018). The maximum fuel temperature in the cores fueled by these three FCM fuels was predicted to be higher than that in the reference 350-MWt mHTGR core in both normal operating conditions and during representative design basis accidents (Lu and Brown, 2019). To better understand the potential safety margins in mHTGR design basis accidents, we performed thermal-hydraulics sensitivity studies to investigate how maximum fuel temperature varies considering various parameters, e.g. thermal properties, within the ranges corresponding to the differences between the FCM-fueled prismatic mHTGR cores and the reference core with conventional fuel compacts. We found that the difference in the steady-state axial power distribution contributed the most to the difference in the maximum fuel temperature, in both normal operation and design basis accidents. Experimental data suggested that the annealing process of irradiation defects in SiC would be rapid at mHTGR relevant fuel temperatures. The bounding potential impact of the SiC annealing on the maximum fuel temperature was analyzed considering both the thermal conductivity recovery and the Wigner energy release due to the annealing of SiC. We found that the defect annealing process in SiC would at most increase the peak maximum fuel temperature of an FCM-fueled core by 40 K in loss of forced cooling accidents and by 10 K in a control rod withdrawal accident. Additional experiments on the SiC defect annealing kinetics and Wigner energy release in more relevant conditions are needed.
Original language | English |
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Pages (from-to) | 125-147 |
Number of pages | 23 |
Journal | Nuclear Engineering and Design |
Volume | 345 |
DOIs | |
State | Published - Apr 15 2019 |
Funding
Notice: This manuscript has been co-authored by UT-Battelle, LLC under Contract No. DE-AC05-00OR22725 and Battelle Energy Alliance, LLC under Contract No. DE-AC07-05ID1451 with the U.S. Department of Energy. The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes. The Department of Energy will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan ( http://energy.gov/downloads/doe-public-access-plan ). This cross-cutting effort was made possible by the synergistic research and development efforts of the U.S. Department of Energy, Office of Nuclear Energy, specifically the Advanced Fuels Campaign, and the Advanced Reactor Technologies Program. The experimental work was supported by the U.S. Department of Energy, Office of Nuclear Energy under DOE Idaho Operations Office Contract DE-AC07- 051D14517 as part of a Nuclear Science User Facilities experiment.
Funders | Funder number |
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Battelle Energy Alliance | DE-AC07-05ID1451 |
U.S. Department of Energy | DE-AC07- 051D14517 |
Office of Nuclear Energy | |
UT-Battelle | DE-AC05-00OR22725 |
Keywords
- Fully Ceramic Microencapsulated (FCM) fuel
- LOFC
- RIA
- Sensitivity study
- SiC annealing
- TRISO fuel