In this work, a two-zone reactor core, which contains an inner driving zone and an outer ThO2 breeding zone, is designed under the framework of the HTR-PM. The main aim of this work is to investigate the feasibility of thorium utilization in the mature design of the HTR-PM with the inherent safety features. The neutronics and thermal-hydraulics characteristics are investigated to optimize the design parameters by using VSOP. The aim of optimization is to maximize the conversion of thorium to 233U in the breeding zone. The preliminary results indicate that the volume ratio of the breeding zone to the driving zone has significant influence on the power peaking factor and the maximum fuel temperature in normal operation and accidental conditions. On the other hand, the increase of reactor power will lead to increase of maximum fuel temperature after DLOFC accident. More heavy metal loading in the breeding zone will raise 233U yield, while the influence of fuel particle radius on the conversion ratio is negligible. An optimized 200 MWt two-zone reactor design is obtained with volume ratio of the driving zone to the breeding zone of 4:1, and 7 g and 30 g heavy metal per fuel sphere in the driving zone and the breeding zone, respectively.
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2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5147-0
PROCEEDINGS PAPER
Preliminary Neutronics and Thermal-Hydraulics Study on Thorium-Based HTR-PM With Outer Breeding Zone
Qiudong Wang,
Qiudong Wang
Tsinghua University, Beijing, China
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Zuoyi Zhang
Zuoyi Zhang
Tsinghua University, Beijing, China
Search for other works by this author on:
Qiudong Wang
Tsinghua University, Beijing, China
Bing Xia
Tsinghua University, Beijing, China
Jiong Guo
Tsinghua University, Beijing, China
Ding She
Tsinghua University, Beijing, China
Lei Shi
Tsinghua University, Beijing, China
Zuoyi Zhang
Tsinghua University, Beijing, China
Paper No:
ICONE26-81975, V005T05A019; 6 pages
Published Online:
October 24, 2018
Citation
Wang, Q, Xia, B, Guo, J, She, D, Shi, L, & Zhang, Z. "Preliminary Neutronics and Thermal-Hydraulics Study on Thorium-Based HTR-PM With Outer Breeding Zone." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues. London, England. July 22–26, 2018. V005T05A019. ASME. https://doi.org/10.1115/ICONE26-81975
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