Neutronics and Accident Analysis of Th-U-MOX Loading in Pebble Bed High-temperature Reactors

Xia Bing; Li Fu; Wei Chunlin; Chen Fubing; Xu Xiaolin; Jing Yingqing

doi:10.13832/j.jnpe.2014.S2.0031

Volume 35 Issue S2

Feb. 2025

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Xia Bing, Li Fu, Wei Chunlin, Chen Fubing, Xu Xiaolin, Jing Yingqing. Neutronics and Accident Analysis of Th-U-MOX Loading in Pebble Bed High-temperature Reactors[J]. Nuclear Power Engineering, 2014, 35(S2): 31-33. doi: 10.13832/j.jnpe.2014.S2.0031

Citation:

Xia Bing, Li Fu, Wei Chunlin, Chen Fubing, Xu Xiaolin, Jing Yingqing. Neutronics and Accident Analysis of Th-U-MOX Loading in Pebble Bed High-temperature Reactors[J]. Nuclear Power Engineering, 2014, 35(S2): 31-33. doi: 10.13832/j.jnpe.2014.S2.0031

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Neutronics and Accident Analysis of Th-U-MOX Loading in Pebble Bed High-temperature Reactors

doi: 10.13832/j.jnpe.2014.S2.0031

Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing, 100084, China

Received Date: 2014-11-06
Rev Recd Date: 2014-12-17

Available Online: 2025-02-15

Abstract

Abstract

The neutronics and accidental features of HTR-PM with Th-U-MOX fuel loading are investigated. The parametric analysis is performed on the uranium fraction in MOX fuel and the C/HM ratio, for the optimization of Th-U-MOX loading. It is revealed that the requirement of natural uranium per energy production decreases when the C/HM ratio decreases. The optimized scheme reduces the uranium requirement for 8.5% and provides thorium utilization as low as 6%.
- Thorium-based fuel cycle,
- Pebble bed high temperature reactor,
- Th-U-MOM fuel,
- Requirement of natural uranium,
- DLOFC