4.5 Article

Fully ceramic microencapsulated fuel in prismatic high-temperature gas-cooled reactors: Design basis accidents and fuel cycle cost

Journal

NUCLEAR ENGINEERING AND DESIGN
Volume 347, Issue -, Pages 108-121

Publisher

ELSEVIER SCIENCE SA
DOI: 10.1016/j.nucengdes.2019.03.022

Keywords

Fully ceramic microencapsulated (FCM) fuel; High-temperature gas-cooled reactor (HTGR); TRISO fuel; Control rod worth; Loss of forced cooling (LOFC) accidents; Reactivity-initiated accidents (RIA); Fuel cost estimation

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Fully ceramic microencapsulated (FCM) fuel may enhance the already strong inherent reactor safety characteristics of a conventional High-Temperature Gas-Cooled Reactor (HTGR). FCM fuel uses an SiC matrix that exhibits higher stability under irradiation with limited swelling relative to a conventional graphite matrix. Additionally, the SiC matrix is expected to exhibit improved mechanical performance relative to graphite. The feasibility of FCM-fueled HTGRs has been explored in a previous study (Lu et al., 2018), and three FCM fuel concepts were identified to be able to maintain the cycle length of the reference conventional General Atomics 350 MWt prismatic modular HTGR. In this work, the previous investigation of the reactor core safety characteristics of HTGRs fueled by these three FCM fuels was significantly extended to detailed thermal hydraulics and neutronics analysis of normal operation and design basis accident scenarios. We found that these FCM-fueled cores would have a maximum fuel temperature similar to 20-40 K higher than that of the reference HTGR core at the beginning of cycle (BOC) and similar to 30-60 K higher at the end of cycle (EOC) during normal operating conditions. Pressurized (P-) and depressurized (D-) loss of forced cooling (LOFC) accidents as well as the control rod withdrawal accident were explored. The FCM-fueled cores would at most have a maximum fuel temperature similar to 30-50 K higher than that of the reference core in a P- LOFC accident, similar to 10-30 K in a D- LOFC accident and similar to 30-50 K in a rod withdrawal accident. The conclusion of the study is that FCM fuel has a small impact on the reactor performance and safety characteristics during normal operation and design basis accident conditions within the existing and generic 350 MWt prismatic modular HTGR design we considered. Additionally, a fuel cycle cost comparison was also performed in the current study. We found that the FCM fuels may be up to 40%-74% more expensive than the conventional fuel. Further analysis of the economics of FCM fuel are needed, because the uncertainties in the assumptions for this study are high.

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