In this study, the multiplication factor and neutron spectrum behaviors were investigated against the moderator-to-fuel ratio, the fuel loading height, and the detector location in HTR-10. The MCNP5 computer code (version 1.51) was employed to perform all the simulation computations. The results revealed that the multiplication factor varies significantly depending on the moderator-to-fuel ratio and the fuel loading height due to the competition among the neutron moderation and absorption abilities of the moderator as well as the neutron production ability of the fuel. Due to its inherent stability, HTR-10 is deliberately designed such that the multiplication factor decreases and the neutron spectrum softens as the moderator-to-fuel ratio increases. The average neutron energy level in the HTR-10 fuel balls is approximately 200 keV and ranges from smallest to largest at the middle, bottom, and top of the reactor core, respectively.
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18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4930-9
PROCEEDINGS PAPER
A Parametric Study of Fuel Lattice Design for HTR-10
Meng-Jen Wang,
Meng-Jen Wang
National Tsing Hua University, Hsinchu, Taiwan
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Jinn-Jer Peir,
Jinn-Jer Peir
National Tsing Hua University, Hsinchu, Taiwan
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Chen-Wei Chi,
Chen-Wei Chi
National Tsing Hua University, Hsinchu, Taiwan
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Jenq-Horng Liang
Jenq-Horng Liang
National Tsing Hua University, Hsinchu, Taiwan
Search for other works by this author on:
Meng-Jen Wang
National Tsing Hua University, Hsinchu, Taiwan
Jinn-Jer Peir
National Tsing Hua University, Hsinchu, Taiwan
Chen-Wei Chi
National Tsing Hua University, Hsinchu, Taiwan
Jenq-Horng Liang
National Tsing Hua University, Hsinchu, Taiwan
Paper No:
ICONE18-29253, pp. 481-485; 5 pages
Published Online:
April 8, 2011
Citation
Wang, M, Peir, J, Chi, C, & Liang, J. "A Parametric Study of Fuel Lattice Design for HTR-10." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 2. Xi’an, China. May 17–21, 2010. pp. 481-485. ASME. https://doi.org/10.1115/ICONE18-29253
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