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

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

doi:10.1002/er.5004

Cited by 5 publications

(8 citation statements)

References 12 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%

“…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: 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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“…In order to breed 233 U in low reactivity fuel assemblies and reduce the power peaking factor, a three‐diamensional 12‐batch shuffling strategy is used for promoting reactivity complementation among high and low reactivity fuel assemblies, as before. Details are given in these literatures 14‐15 …”

Section: Model and Methodologymentioning

confidence: 99%

“…Our previous research found that FNaBe salt (57%NaF‐43%BeF 2 ) was a remarkable coolant for LSFR core and the design of a self‐sustaining core for LSFR core with thorium‐based fuel is accomplishable 13 . Moreover, in further research, the LSFR core based on thorium fuel cycle is favorable for its high discharge burn‐up of 20% to 30% FIMA (Fissions per Initial heavy Metal Atom) or about 200 to 300 MWd/kg IHM (Initial Heavy Metal), small reactivity swing over the whole lifetime, the negative reactivity temperature coefficient, and accepted cladding peak radiation damage 14‐15 . Therefore, the LSFR core is a good alternative option for the deployment of a self‐sustained thorium‐based nuclear system.…”

Section: Introductionmentioning

confidence: 95%

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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An algorithm for accurate modeling and simulating reactor cores with involute‐shaped fuel plates by Monte Carlo

et al. 2021

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Summary A real three‐dimensional representation of reactor core with involute fuel plates via Monte Carlo method is still lacking at the present, and usually equivalent homogeneous models of water coolants and simplified fuel plate shapes have been used. This work proposed an algorithm to simulate the reactor core composed of involute fuel plates with an explicit accurate description of its involute surfaces. The description of involute surfaces is through its governing equations. The mathematical function methods to depict the involute curves and the schemes to compute the distance between any neutron particle and an involute surface along a ray are presented and demonstrated step‐by‐step. The algorithm is realized in the Monte Carlo code and validated by the published data of a high flux isotope reactor. This study definitively provides a method to model the involute fuel plates in the Monte Carlo simulation.

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

Cited by 5 publications

References 12 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

An algorithm for accurate modeling and simulating reactor cores with involute‐shaped fuel plates by Monte Carlo

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