Technical Briefs

A Parametric Study of Fuel Lattice Design for HTR-10

[+] Author and Article Information
Meng-Jen Wang, Chen-Wei Chi, Jenq-Horng Liang

Institute of Nuclear Engineering and Science, National Tsing Hua University, Hsinchu, Taiwan 30013, R.O.C.

Jinn-Jer Peir1

Nuclear Science and Technology Development Center, National Tsing Hua University, Hsinchu, Taiwan 30013, R.O.C.


Corresponding author.

J. Eng. Gas Turbines Power 133(8), 084503 (Apr 11, 2011) (4 pages) doi:10.1115/1.4002879 History: Received July 02, 2010; Revised July 07, 2010; Published April 11, 2011; Online April 11, 2011

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 high-temperature gas-cooled reactor (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 240 keV and ranges from smallest to largest at the middle, bottom, and top of the reactor core, respectively.

Copyright © 2011 by American Society of Mechanical Engineers
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Grahic Jump Location
Figure 1

Top view of fuel and TRISO particles’ lattice designs

Grahic Jump Location
Figure 2

Multiplication factor versus moderator-to-fuel ratio for various fuel loadings

Grahic Jump Location
Figure 3

Neutron spectra for various detector locations and moderator-to-fuel ratios



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