Overview of the physics design of the EHL-2 spherical torus

ENN is planning the next generation experimental device EHL-2 with the goal to verify the thermal reaction rates of p- 11 B fusion, establish spherical torus/tokamak experimental scaling laws at 10’s keV ion temperature, and provide a design basis for subsequent experiments to test and realize the p...

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Published inPlasma science & technology Vol. 27; no. 2; pp. 24001 - 24020
Main Authors LIANG, Yunfeng, XIE, Huasheng, SHI, Yuejiang, GU, Xiang, JIANG, Xinchen, DONG, Lili, WANG, Xueyun, YANG, Danke, LIU, Wenjun, SUN, Tiantian, WANG, Yumin, LI, Zhi, CAI, Jianqing, SONG, Xianming, TAN, Muzhi, YANG, Guang, ZHAO, Hanyue, DONG, Jiaqi, PENG, Yueng-Kay Martin, SONG, Shaodong, CHEN, Zhengyuan, LI, Yingying, LIU, Bing, LUO, Di, YANG, Yuanming, LIU, Minsheng, Team, the EHL-2
Format Journal Article
LanguageEnglish
Published Plasma Science and Technology 01.02.2025
Subjects
Online AccessGet full text
ISSN1009-0630
2058-6272
DOI10.1088/2058-6272/ad981a

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Abstract ENN is planning the next generation experimental device EHL-2 with the goal to verify the thermal reaction rates of p- 11 B fusion, establish spherical torus/tokamak experimental scaling laws at 10’s keV ion temperature, and provide a design basis for subsequent experiments to test and realize the p- 11 B fusion burning plasma. Based on 0-dimensional (0-D) system design and 1.5-dimensional transport modelling analyses, the main target parameters of EHL-2 have been basically determined, including the plasma major radius, R 0 , of 1.05 m, the aspect ratio, A , of 1.85, the maximum central toroidal magnetic field strength, B 0 , of 3 T, and the plasma toroidal current, I p , of 3 MA. The main heating system will be the neutral beam injection at a total power of 17 MW. In addition, 6 MW of electron cyclotron resonance heating will serve as the main means of local current drive and MHD instabilities control. The physics design of EHL-2 is focused on addressing three main operating scenarios, i.e., (1) high ion temperature scenario, (2) high-performance steady-state scenario and (3) high triple product scenario. Each scenario will integrate solutions to different important issues, including equilibrium configuration, heating and current drive, confinement and transport, MHD instability, p- 11 B fusion reaction, plasma-wall interactions, etc. Beyond that, there are several unique and significant challenges to address, including establish a plasma with extremely high core ion temperature ( T i,0 > 30 keV), and ensure a large ion-to-electron temperature ratio ( T i,0 / T e,0 > 2), and a boron concentration of 10%‒15% at the plasma core; realize the start-up by non-inductive current drive and the rise of MA-level plasma toroidal current. This is because the volt-seconds that the central solenoid of the ST can provide are very limited; achieve divertor heat and particle fluxes control including complete detachment under high P / R (> 20 MW/m) at relatively low electron densities. This overview will introduce the advanced progress in the physics design of EHL-2.
AbstractList ENN is planning the next generation experimental device EHL-2 with the goal to verify the thermal reaction rates of p- 11 B fusion, establish spherical torus/tokamak experimental scaling laws at 10’s keV ion temperature, and provide a design basis for subsequent experiments to test and realize the p- 11 B fusion burning plasma. Based on 0-dimensional (0-D) system design and 1.5-dimensional transport modelling analyses, the main target parameters of EHL-2 have been basically determined, including the plasma major radius, R 0 , of 1.05 m, the aspect ratio, A , of 1.85, the maximum central toroidal magnetic field strength, B 0 , of 3 T, and the plasma toroidal current, I p , of 3 MA. The main heating system will be the neutral beam injection at a total power of 17 MW. In addition, 6 MW of electron cyclotron resonance heating will serve as the main means of local current drive and MHD instabilities control. The physics design of EHL-2 is focused on addressing three main operating scenarios, i.e., (1) high ion temperature scenario, (2) high-performance steady-state scenario and (3) high triple product scenario. Each scenario will integrate solutions to different important issues, including equilibrium configuration, heating and current drive, confinement and transport, MHD instability, p- 11 B fusion reaction, plasma-wall interactions, etc. Beyond that, there are several unique and significant challenges to address, including establish a plasma with extremely high core ion temperature ( T i,0 > 30 keV), and ensure a large ion-to-electron temperature ratio ( T i,0 / T e,0 > 2), and a boron concentration of 10%‒15% at the plasma core; realize the start-up by non-inductive current drive and the rise of MA-level plasma toroidal current. This is because the volt-seconds that the central solenoid of the ST can provide are very limited; achieve divertor heat and particle fluxes control including complete detachment under high P / R (> 20 MW/m) at relatively low electron densities. This overview will introduce the advanced progress in the physics design of EHL-2.
Author DONG, Lili
WANG, Yumin
JIANG, Xinchen
LIANG, Yunfeng
SHI, Yuejiang
Team, the EHL-2
LI, Yingying
YANG, Yuanming
SONG, Shaodong
XIE, Huasheng
CAI, Jianqing
CHEN, Zhengyuan
DONG, Jiaqi
TAN, Muzhi
ZHAO, Hanyue
SUN, Tiantian
LUO, Di
LIU, Wenjun
LI, Zhi
LIU, Minsheng
WANG, Xueyun
PENG, Yueng-Kay Martin
GU, Xiang
SONG, Xianming
YANG, Guang
YANG, Danke
LIU, Bing
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  organization: Hebei Key Laboratory of Compact Fusion, Langfang 065001, People’s Republic of China
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Snippet ENN is planning the next generation experimental device EHL-2 with the goal to verify the thermal reaction rates of p- 11 B fusion, establish spherical...
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SubjectTerms alpha particles
proton-boron fusion
spherical torus
thermal reaction rate
Title Overview of the physics design of the EHL-2 spherical torus
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