Minor actinide transmutation in a board type sodium cooled breed and burn reactor core

Zheng, Meiyin; Tian, Wenxi; Zhang, Dalin; Qiu, Suizheng; Su, G.H.

doi:10.1016/j.anucene.2015.03.024

Cited by 12 publications

(3 citation statements)

References 22 publications

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“…Previous research at Xi'an Jiaotong University proposed the concept of sodium cooled checkerboard type Breed and Burn reactor (Zheng et al, 2014a,b) and performed MA transmutation analysis based on this concept (Zheng et al, 2015). The so-called checkerboard type means that a number of breeding assemblies are arranged in the inner core in a scattered way to increase the breeding ability of the core.…”

Section: Core Descriptionmentioning

confidence: 99%

“…The first SWR core design was conducted at Brookhaven National Laboratory (BNL) in collaboration with the Massachusetts Institute of Technology (MIT) in 1970s. After that, the studies of SWR were performed by Marshall et al (2005), Greenspan and Heidet (2009), Chen et al (2011), Greenspan (2012, 2013), Qvist and Greenspan (2012), Zhang et al (2013), Zheng et al (2014aZheng et al ( , 2014bZheng et al ( , 2015, and so on. In 2008, the Terra Power LLC was founded to develop commercial TWR (actually SWR), which brings a huge boost to the investigation of Breed and Burn reactors.…”

Section: Introductionmentioning

confidence: 99%

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Performance of radial fuel shuffling sodium cooled Breed and Burn reactor core

Zheng

Tian

Zhang

et al. 2016

Annals of Nuclear Energy

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a b s t r a c tIn this paper, performance of radial fuel shuffling of sodium cooled Breed and Burn reactor core is investigated. Neutronics and depletion calculations are carried out by MCORE based on the ENDF/B-VII data library. Thermal-hydraulic analysis is performed based on a self-developed parallel channels model steady-state code SAST. First of all, the assembly parameters are optimized from neutronics and thermal-hydraulics. The results show that assembly with 127 fuel rods and P/D of 1.12 is the best design. Secondly, the core critical features and radial power peaking factors of the inward and outward fuel shuffling strategy under different fuel shuffling periods are carried out. The results show that k eff of the beginning of equilibrium cycle (BOEC) and end of equilibrium cycle (EOEC) of both the inward and outward fuel shuffling strategy parabolically vary with the fuel shuffling period. Power peaking factor of the inward fuel shuffling strategy decreases with the increase of fuel shuffling period exponentially, while that of the outward fuel shuffling strategy increases with the fuel shuffling period exponentially. The outward fuel shuffling strategy with shuffling period of 500 days performs better in core critical features and radial power peaking factors. Reactivity coefficients of the optimized core are calculated. Finally, preliminary thermal-hydraulic analysis of the optimized core is performed. The results show that maximum cladding interface temperature and maximum fuel temperature are all within the acceptable limits.

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Section: Core Descriptionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Performance of radial fuel shuffling sodium cooled Breed and Burn reactor core

Zheng

Tian

Zhang

et al. 2016

Annals of Nuclear Energy

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“…Spent nuclear fuel containing long‐lived fission products (LLFPs) is one of the most important issues restricting the development of nuclear energy 7,8 . Because of its large radiotoxicity coefficient (8.5 × 10 −2 Sv/g), long half‐life ( T 1/2 = 2.3 × 10 6 years) as well as high annual production (e.g., 7.5 kg/(GWe∙y) for a pressurized water reactor), 9,10 135 Cs is considered as one of the most important LLFPs.…”

Section: Introductionmentioning

confidence: 99%

Transmutation of ¹³⁵ Cs in a single‐fluid double‐zone thorium molten salt reactor

Chen

et al. 2020

Int J Energy Res

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Summary The single‐fluid double‐zone thorium molten salt reactor (SD‐TMSR) allows for online reprocessing fission products and adding nuclear fuel, which provides a high Th‐U breeding capability for thorium utilization. Although 135Xe in the core can be online extracted by the helium bubbling system during reactor operation to improve the reactor neutron economy, it would decay to the long‐lived 135Cs with a half‐life of 2.3 × 106 years, which is undesired from the viewpoint of the development of nuclear energy. The total production of 135Cs decayed from the extracted 135Xe is about 1.83 tons for the SD‐TMSR after 60 years operation. To reduce the significant accumulation of 135Cs, we propose a cooling transmutation method, by which the produced 135Cs is reinjected into the core for transmutation. First, a separation and multigroup cooling system in the SD‐TMSR is adopted to enhance the mass fraction of decayed 135Cs in the total Cs isotopes from 29% to 75%. Then, the separated Cs isotopes with optimized mass fraction of 135Cs are online injected into the core for transmutation. The total transmuted mass of 135Cs is about 0.61 tons after 60 years operation, corresponding to the transmuted fraction of about 37.42% and the transmutation rate of 10.17 kg/(GWe y). Moreover, the net 233U production is about 2.03 tons which is much larger than the initial 233U loading inventory of the SD‐TMSR, indicating that the Th‐U breeding mode for the transmutation of 135Cs in the SD‐TMSR can be achieved over 60 years. Novelty Statement “Transmutation of 135Cs in a single‐fluid double‐zone thorium molten salt reactor” was investigated by Kunfeng Ma, Chenggang Yu*, Jingen Chen*, and Xiangzhou Cai. A cooling transmutation method is performed to reduce the 135Cs decayed from 135Xe outside of core. It is found that a separation and multigroup cooling system improves the mass fraction of 135Cs in the total Cs isotopes from 29% to 75% and an online returning 135Cs transmutation scenario transmutes about 0.61 tons of 135Cs over 60 years.

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Minor Actinides Incineration in a Small Molten Salt Fast Reactor

Zou

et al. 2017

Proceedings of the 20th Pacific Basin Nuclear Conference

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Minor actinide transmutation in a board type sodium cooled breed and burn reactor core

Cited by 12 publications

References 22 publications

Performance of radial fuel shuffling sodium cooled Breed and Burn reactor core

Performance of radial fuel shuffling sodium cooled Breed and Burn reactor core

Transmutation of ¹³⁵ Cs in a single‐fluid double‐zone thorium molten salt reactor

Minor Actinides Incineration in a Small Molten Salt Fast Reactor

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Minor actinide transmutation in a board type sodium cooled breed and burn reactor core

Cited by 12 publications

References 22 publications

Performance of radial fuel shuffling sodium cooled Breed and Burn reactor core

Performance of radial fuel shuffling sodium cooled Breed and Burn reactor core

Transmutation of 135 Cs in a single‐fluid double‐zone thorium molten salt reactor

Minor Actinides Incineration in a Small Molten Salt Fast Reactor

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Transmutation of ¹³⁵ Cs in a single‐fluid double‐zone thorium molten salt reactor