Study on the effect of neutron shielding design on tritium breeding based on water-cooled ceramic blanket for CFETR

The Chinese Fusion Engineering Test Reactor (CFETR) is a magnetic confinement fusion reactor independently designed and developed by China, which is based on the ITER design experience. As one of the candidates for the CFETR, the water cooled ceramic blanket (WCCB) mainly carries out many important...

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Main Authors: Jie Li, Hang Li, Muquan Wu, Xiang Zhu, Peiguang Yan, Xiaodong Lin, Jie Zhang, Xiang Gao
Format: Article
Language:English
Published: AIP Publishing LLC 2023-07-01
Series:AIP Advances
Online Access:http://dx.doi.org/10.1063/5.0158174
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author Jie Li
Hang Li
Muquan Wu
Xiang Zhu
Peiguang Yan
Xiaodong Lin
Jie Zhang
Xiang Gao
author_facet Jie Li
Hang Li
Muquan Wu
Xiang Zhu
Peiguang Yan
Xiaodong Lin
Jie Zhang
Xiang Gao
author_sort Jie Li
collection DOAJ
description The Chinese Fusion Engineering Test Reactor (CFETR) is a magnetic confinement fusion reactor independently designed and developed by China, which is based on the ITER design experience. As one of the candidates for the CFETR, the water cooled ceramic blanket (WCCB) mainly carries out many important tasks, such as tritium breeding and radiation shielding. The high tritium breeding ability is one of the most significant goals of the blanket. For the design of the CFETR, in addition to meeting the requirements of tritium breeding, the design of the blanket must also consider meeting relevant shielding limits. Due to the limited space of the blanket, the improvement in tritium breeding space will inevitably lead to the reduction in neutron shielding space behind the breeding area, and vice versa. Therefore, under the premise of meeting the requirements of neutron shielding, increasing the tritium breeding space as much as possible is the focus of research. In this work, a three-dimensional neutronics model containing the WCCB blanket is developed, and the neutronics performance is calculated based on 1.5 GW fusion power. A set of nuclear analyses are carried out by the MCNP code, including analysis of the neutron wall load, tritium breeding ratio (TBR), and fast neutron fluence of the TF coil. It is found that the shielding space of certain blanket modules could be optimized. After the shielding optimization, the global TBR increased from 1.168 to 1.186, an increase of 0.018 TBR. The current research has important guiding significance for the future design and optimization of the WCCB for the CFETR.
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spelling doaj.art-c6c6a0ec5f854b40a59b744823830a912023-08-02T20:06:09ZengAIP Publishing LLCAIP Advances2158-32262023-07-01137075209075209-810.1063/5.0158174Study on the effect of neutron shielding design on tritium breeding based on water-cooled ceramic blanket for CFETRJie Li0Hang Li1Muquan Wu2Xiang Zhu3Peiguang Yan4Xiaodong Lin5Jie Zhang6Xiang Gao7College of Physics and Optoelectronic Engineering, Shenzhen University, Shenzhen 518060, ChinaCollege of Physics and Optoelectronic Engineering, Shenzhen University, Shenzhen 518060, ChinaCollege of Physics and Optoelectronic Engineering, Shenzhen University, Shenzhen 518060, ChinaCollege of Physics and Optoelectronic Engineering, Shenzhen University, Shenzhen 518060, ChinaCollege of Physics and Optoelectronic Engineering, Shenzhen University, Shenzhen 518060, ChinaCollege of Physics and Optoelectronic Engineering, Shenzhen University, Shenzhen 518060, ChinaInstitute of Plasma Physics, Chinese Academic Sciences, Hefei 230026, ChinaCollege of Physics and Optoelectronic Engineering, Shenzhen University, Shenzhen 518060, ChinaThe Chinese Fusion Engineering Test Reactor (CFETR) is a magnetic confinement fusion reactor independently designed and developed by China, which is based on the ITER design experience. As one of the candidates for the CFETR, the water cooled ceramic blanket (WCCB) mainly carries out many important tasks, such as tritium breeding and radiation shielding. The high tritium breeding ability is one of the most significant goals of the blanket. For the design of the CFETR, in addition to meeting the requirements of tritium breeding, the design of the blanket must also consider meeting relevant shielding limits. Due to the limited space of the blanket, the improvement in tritium breeding space will inevitably lead to the reduction in neutron shielding space behind the breeding area, and vice versa. Therefore, under the premise of meeting the requirements of neutron shielding, increasing the tritium breeding space as much as possible is the focus of research. In this work, a three-dimensional neutronics model containing the WCCB blanket is developed, and the neutronics performance is calculated based on 1.5 GW fusion power. A set of nuclear analyses are carried out by the MCNP code, including analysis of the neutron wall load, tritium breeding ratio (TBR), and fast neutron fluence of the TF coil. It is found that the shielding space of certain blanket modules could be optimized. After the shielding optimization, the global TBR increased from 1.168 to 1.186, an increase of 0.018 TBR. The current research has important guiding significance for the future design and optimization of the WCCB for the CFETR.http://dx.doi.org/10.1063/5.0158174
spellingShingle Jie Li
Hang Li
Muquan Wu
Xiang Zhu
Peiguang Yan
Xiaodong Lin
Jie Zhang
Xiang Gao
Study on the effect of neutron shielding design on tritium breeding based on water-cooled ceramic blanket for CFETR
AIP Advances
title Study on the effect of neutron shielding design on tritium breeding based on water-cooled ceramic blanket for CFETR
title_full Study on the effect of neutron shielding design on tritium breeding based on water-cooled ceramic blanket for CFETR
title_fullStr Study on the effect of neutron shielding design on tritium breeding based on water-cooled ceramic blanket for CFETR
title_full_unstemmed Study on the effect of neutron shielding design on tritium breeding based on water-cooled ceramic blanket for CFETR
title_short Study on the effect of neutron shielding design on tritium breeding based on water-cooled ceramic blanket for CFETR
title_sort study on the effect of neutron shielding design on tritium breeding based on water cooled ceramic blanket for cfetr
url http://dx.doi.org/10.1063/5.0158174
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