Sustainable supply of 99Mo source in a 2 MW molten salt reactor using low-enriched uranium

Chenggang Yu; Chunyan Zou; Chen Wu; Jianhui Wu; Xiangzhou Cai; Jingen Chen

doi:10.1016/j.apradiso.2020.109134

Sustainable supply of ⁹⁹Mo source in a 2 MW molten salt reactor using low-enriched uranium

Appl Radiat Isot. 2020 Jun:160:109134. doi: 10.1016/j.apradiso.2020.109134. Epub 2020 Mar 19.

Authors

Chenggang Yu¹, Chunyan Zou², Chen Wu², Jianhui Wu¹, Xiangzhou Cai², Jingen Chen³

Affiliations

¹ Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai, 201800, China; CAS Innovative Academy in TMSR Energy System, Chinese Academy of Sciences, Shanghai 201800, China.
² Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai, 201800, China; CAS Innovative Academy in TMSR Energy System, Chinese Academy of Sciences, Shanghai 201800, China; University of Chinese Academy of Sciences, Beijing, 100049, China.
³ Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai, 201800, China; CAS Innovative Academy in TMSR Energy System, Chinese Academy of Sciences, Shanghai 201800, China; University of Chinese Academy of Sciences, Beijing, 100049, China. Electronic address: chenjg@sinap.ac.cn.

PMID: 32351226
DOI: 10.1016/j.apradiso.2020.109134

Abstract

The ⁹⁹Mo production in a 2 MW molten salt reactor using liquid low-enriched uranium (LEU) fuel has been evaluated. The batch-wise extraction period of ⁹⁹Mo is optimized to be one day corresponding to 9415 6-day Ci/week of the ⁹⁹Mo production rate. The required amount of uranium is only 4.77 kg annually. The required chemically reprocessed amount of FPs is about 58.4 g annually, accounting for only 4.9% of the solid LEU target method under the identical production capacity of ⁹⁹Mo.

Keywords: (99)Mo supply; Low-enriched uranium; Molten salt reactor.