Neutronics physics analysis of a large fluoride-salt-cooled solid-fuel fast reactor with Th-based fuel

Peng, Yi; Zhu, Guifeng; Zou, Yang; Liu, Sijia; Xu, Hongjie

doi:10.1007/s41365-017-0321-9

Cited by 3 publications

(9 citation statements)

References 19 publications

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“…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 . A calculation is started with a guess on the initial for the leakage rate of active core from MCNP5 calculation.…”

Section: Model and Methodologymentioning

confidence: 96%

“…The LSFR core concept adopted in this study is the same with the preliminary design in 14 which is a large reactor core with low leakage rate. It uses UC/ThC ceramic fuel, a fuel nominal density of 13.6/10.6 g/cm 3 and a smear density of 85%.…”

Section: Model and Methodologymentioning

confidence: 99%

“…Aiming at decreasing the power peaking factor (ppf) and breeding 233 U in low reactivity fuel assemblies, a 3D 12‐batch shuffling scheme is used for promoting reactivity sharing between high and low reactivity fuel assemblies, as before. Details are discussed in literature 14 …”

Section: Model and Methodologymentioning

confidence: 99%

“…Moreover, it could associate advanced high‐temperature reactor (AHTR) nuclear plant design with traditional metal‐clad‐fuel fast reactor cores for near‐term industrial implication and adopts the fluoride salts as coolant to improve the economics of fast reactors. In preliminary research, we found that LSFR reactor core based on thorium fuel with once‐through fuel cycle could achieve a self‐sustaining core and have excellent neutronics characteristics including negative reactivity temperature coefficients at equilibrium, high discharge burnup and small reactivity swing during the reactor lifespan 14‐16 …”

Section: Introductionmentioning

confidence: 99%

“…It is noticed that the post‐reprocessing with close fuel cycle would commonly be an integral part of a sustainable thorium/uranium fuel cycle. Our previous works have centered on the feasibility study for thorium breeding in the LSFR core and neutronic characteristics at equilibrium with once‐through fuel cycle 14‐16 . However, uncertainty still remains as to maintain the sustaining core and the LSFR core safety performance during the fuel multi‐recycle.…”

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: 96%

Section: Model and Methodologymentioning

confidence: 99%

Section: Model and Methodologymentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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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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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High-resolution neutronics model for 238Pu production in high-flux reactors

Pan,

Zhao,

Wang

et al. 2024

NUCL SCI TECH

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Neutronics physics analysis of a large fluoride-salt-cooled solid-fuel fast reactor with Th-based fuel

Cited by 3 publications

References 19 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

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

High-resolution neutronics model for 238Pu production in high-flux reactors

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