Exploratory tritium breeding performance study on a water cooled lead ceramic breeder blanket for EU DEMO using Serpent-2

Yudong Lu; Minyou Ye; Guangming Zhou; Francisco A. Hernández; Jaakko Leppänen; Yuan Hu

doi:10.1016/j.nme.2021.101050

Exploratory tritium breeding performance study on a water cooled lead ceramic breeder blanket for EU DEMO using Serpent-2

Yudong Lu
, Minyou Ye^*
, Guangming Zhou^*
, Francisco A. Hernández
, Jaakko Leppänen
, Yuan Hu

^*Corresponding author for this work

Research output: Contribution to journal › Article › Scientific › peer-review

3 Citations (Scopus)

152 Downloads (Pure)

Abstract

Innovative Water cooled Lead Ceramic Breeder (WLCB) blanket concepts are being developed at Karlsruhe Institute of Technology (KIT) to explore alternative options for the European demonstration fusion power plant (DEMO). Compared to the Helium Cooled Pebble Bed blanket (HCPB, which is one of the two driver blanket concepts of the European DEMO), Lead/ Lead-alloy is used as neutron multiplier instead of Be/Be-alloy and pressurized subcooled water is used as coolant instead of Helium in the WLCB. The tritium self-sufficiency is the vital function that a Breeding Blanket has to achieve. The absorption of neutrons by water leads to a decrease in the number of neutrons, so the requirement to improve the tritium breeding capacity of the water-cooled blankets is particularly prominent. The Monte Carlo neutron transport code Serpent-2 developed by VTT in Finland has already been benchmarked to be applicable to neutronics calculations in the fusion reactors in a previous study. In this paper, an exploratory TBR study on Water cooled Lead Ceramic Breeder Blanket is presented.

Original language	English
Article number	101050
Journal	Nuclear Materials and Energy
Volume	28
Early online date	3 Aug 2021
DOIs	https://doi.org/10.1016/j.nme.2021.101050
Publication status	Published - Sept 2021
MoE publication type	A1 Journal article-refereed

Funding

This work has partly been funded by the National Key Research, Development Program of China (Grant No.: 2017YFE0301501 and No.: 2017YFE0301305 ) and China Scholarship Council (No.: 201806340163 ). This work has also received funding from the Euratom research and training programme 2014-2018 and 2019-2020 under grant agreement No 633053.

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

SDG 7 Affordable and Clean Energy

Keywords

Neutronics
Serpent-2
Tritium breeding
Water cooled Lead Ceramic Breeder

Access to Document

10.1016/j.nme.2021.101050Licence: CC BY-NC-ND

j.nme.2021.101050Final published version, 917 KBLicence: CC BY-NC-ND

Cite this

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title = "Exploratory tritium breeding performance study on a water cooled lead ceramic breeder blanket for EU DEMO using Serpent-2",

abstract = "Innovative Water cooled Lead Ceramic Breeder (WLCB) blanket concepts are being developed at Karlsruhe Institute of Technology (KIT) to explore alternative options for the European demonstration fusion power plant (DEMO). Compared to the Helium Cooled Pebble Bed blanket (HCPB, which is one of the two driver blanket concepts of the European DEMO), Lead/ Lead-alloy is used as neutron multiplier instead of Be/Be-alloy and pressurized subcooled water is used as coolant instead of Helium in the WLCB. The tritium self-sufficiency is the vital function that a Breeding Blanket has to achieve. The absorption of neutrons by water leads to a decrease in the number of neutrons, so the requirement to improve the tritium breeding capacity of the water-cooled blankets is particularly prominent. The Monte Carlo neutron transport code Serpent-2 developed by VTT in Finland has already been benchmarked to be applicable to neutronics calculations in the fusion reactors in a previous study. In this paper, an exploratory TBR study on Water cooled Lead Ceramic Breeder Blanket is presented.",

keywords = "Neutronics, Serpent-2, Tritium breeding, Water cooled Lead Ceramic Breeder",

author = "Yudong Lu and Minyou Ye and Guangming Zhou and Hern{\'a}ndez, \{Francisco A.\} and Jaakko Lepp{\"a}nen and Yuan Hu",

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year = "2021",

month = sep,

doi = "10.1016/j.nme.2021.101050",

language = "English",

volume = "28",

journal = "Nuclear Materials and Energy",

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AU - Lu, Yudong

AU - Ye, Minyou

AU - Zhou, Guangming

AU - Hernández, Francisco A.

AU - Leppänen, Jaakko

AU - Hu, Yuan

PY - 2021/9

Y1 - 2021/9

N2 - Innovative Water cooled Lead Ceramic Breeder (WLCB) blanket concepts are being developed at Karlsruhe Institute of Technology (KIT) to explore alternative options for the European demonstration fusion power plant (DEMO). Compared to the Helium Cooled Pebble Bed blanket (HCPB, which is one of the two driver blanket concepts of the European DEMO), Lead/ Lead-alloy is used as neutron multiplier instead of Be/Be-alloy and pressurized subcooled water is used as coolant instead of Helium in the WLCB. The tritium self-sufficiency is the vital function that a Breeding Blanket has to achieve. The absorption of neutrons by water leads to a decrease in the number of neutrons, so the requirement to improve the tritium breeding capacity of the water-cooled blankets is particularly prominent. The Monte Carlo neutron transport code Serpent-2 developed by VTT in Finland has already been benchmarked to be applicable to neutronics calculations in the fusion reactors in a previous study. In this paper, an exploratory TBR study on Water cooled Lead Ceramic Breeder Blanket is presented.

AB - Innovative Water cooled Lead Ceramic Breeder (WLCB) blanket concepts are being developed at Karlsruhe Institute of Technology (KIT) to explore alternative options for the European demonstration fusion power plant (DEMO). Compared to the Helium Cooled Pebble Bed blanket (HCPB, which is one of the two driver blanket concepts of the European DEMO), Lead/ Lead-alloy is used as neutron multiplier instead of Be/Be-alloy and pressurized subcooled water is used as coolant instead of Helium in the WLCB. The tritium self-sufficiency is the vital function that a Breeding Blanket has to achieve. The absorption of neutrons by water leads to a decrease in the number of neutrons, so the requirement to improve the tritium breeding capacity of the water-cooled blankets is particularly prominent. The Monte Carlo neutron transport code Serpent-2 developed by VTT in Finland has already been benchmarked to be applicable to neutronics calculations in the fusion reactors in a previous study. In this paper, an exploratory TBR study on Water cooled Lead Ceramic Breeder Blanket is presented.

KW - Neutronics

KW - Serpent-2

KW - Tritium breeding

KW - Water cooled Lead Ceramic Breeder

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DO - 10.1016/j.nme.2021.101050

M3 - Article

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SN - 2352-1791

VL - 28

JO - Nuclear Materials and Energy

JF - Nuclear Materials and Energy

M1 - 101050

ER -

Exploratory tritium breeding performance study on a water cooled lead ceramic breeder blanket for EU DEMO using Serpent-2

Abstract

Funding

UN SDGs

Keywords

Access to Document

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