Sustainability of thorium-uranium in pebble-bed fluoride salt-cooled high temperature reactor

Zhu, Guifeng; Zou, Yang; Xu, Hongjie

doi:10.1051/epjn/e2015-50032-6

Cited by 5 publications

(2 citation statements)

References 23 publications

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“…MOBAT code system was developed for burnup analysis for arbitrary core models. Its correctness and effectiveness have been intensively proved 17 . The flow chart of the equilibrium LSFR reference core as shown in Figure 4 was the same with the previous study for detailed description in the previous papers 14,16 .…”

Section: Model and Methodologymentioning

confidence: 80%

“…The TRISO‐based pebble bed fluoride‐salt‐cooled high‐temperature reactor (PB‐FHR) is not suitable for thorium/uranium breeding due to low fuel loading (not beyond 5 vol%) and strong neutron moderating ability. Guifeng Zhu et al 9‐10 put forward a new thorium/uranium breeding PB‐FHR using dispersion fuel particles. Their study suggested that the maximum discharge burnup for dispersion‐based PB‐FHR was more than 200 MWd/kgHM whereas keeping thorium‐uranium sustainable and coolant temperature reactivity coefficient negative.…”

Section: Introductionmentioning

confidence: 99%

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Thorium‐uranium close fuel cycle in fluoride‐salt‐cooled solid‐fuel fast reactor with two recycle strategies

et al. 2020

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Summary Fluoride‐salt‐cooled solid‐fuel fast reactor (LSFR) based on thorium fuel could achieve a self‐sustaining core which satisfies long term energy supply. In this paper, we further investigated the LSFR core neutronics characteristics for the close fuel cycle from the 0th cycle core to the 8th cycle core. Two fuel recycle schemes, including U recycling and U/Pu/MA recycling, were put forward to evaluate physical effects caused by these recycling elements. It was found that both closed fuel recycle schemes gained self‐sustaining core and reduced the 233U fuel loading, indicating that recycling nuclides could partially replace 233U. Due to the lower 233U loading in fuel cycle process, the breeding performance of LSFR core was better and U/Pu/MA recycling scheme possessed more advantages. The LSFR core could not transmute MA due to the relatively soft fast energy spectrum. The U/Pu/MA recycle scheme accumulated more transuranium elements with cycle burnup than that of U recycle scheme.

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Section: Model and Methodologymentioning

confidence: 80%

Section: Introductionmentioning

confidence: 99%

Thorium‐uranium close fuel cycle in fluoride‐salt‐cooled solid‐fuel fast reactor with two recycle strategies

et al. 2020

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Core neutronic characterization of a large molten‐salt cooled thorium‐based solid fuel fast reactor

et al. 2020

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Spent fuel characteristics for thorium‐uranium recycle in fluoride‐salt‐cooled solid‐fuel fast reactor

et al. 2021

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Summary Fluoride‐salt‐cooled solid‐fuel fast reactor (LSFR) with thorium‐based fuel could complete a self‐sustaining core that fulfills long‐term energy demands. This paper further investigated the LSFR core sustainability of breeding thorium and the spent fuel characteristics for closed fuel cycle. Two fuel recycle strategies were proposed in this paper, including U recycling and U/Pu/MA recycling, to evaluate the physical effects caused by these recycling some highly radiotoxic and heat producing minor actinides. Based on the two fuel management strategies, the sustainability of breeding thorium and the spent fuel characteristics from the 0th cycle core to the 8th cycle core were assessed, including radioactivity, radiotoxicity, and decay heat. It was found that both recycle strategies accomplished good breeding performance and reduced the 233U fuel inventory, implying that recycling nuclides could partially replace 233U. The U/Pu/MA recycling scheme possessed slightly better advantages in lower 233U loading and breeding performance, but this scheme accumulated more transuranium elements with cycle burnup because the LSFR core could not transmute MA for its relatively soft fast energy spectrum. In spite of this, the level of radioactivity, radiotoxicity, and decay heat for the discharge fuel in the 8th cycle core was either lower than or comparable to that of traditional PWR. It is worthwhile mentioning that between 1000 and 100 000 years the radioactivity, radiotoxicity, and decay heat production tend to grow again, which might require sophisticated storage design for LSFR core with thorium‐based fuel in the future.

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Sustainability of thorium-uranium in pebble-bed fluoride salt-cooled high temperature reactor

Cited by 5 publications

References 23 publications

Thorium‐uranium close fuel cycle in fluoride‐salt‐cooled solid‐fuel fast reactor with two recycle strategies

Thorium‐uranium close fuel cycle in fluoride‐salt‐cooled solid‐fuel fast reactor with two recycle strategies

Core neutronic characterization of a large molten‐salt cooled thorium‐based solid fuel fast reactor

Spent fuel characteristics for thorium‐uranium recycle in fluoride‐salt‐cooled solid‐fuel fast reactor

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