Analysis of nuclear response in CFETR toroidal field coils with density reduction VR technique

Lu, Peng; Xu, Kun; Zheng, Y.; Li, Xia; Liu, Songlin; Huang, Jianjun; Yu, Bin

doi:10.1016/j.fusengdes.2019.111243

Cited by 7 publications

(7 citation statements)

References 13 publications

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“…On the other hand, the radiation damage to the TF conductor and insulator is also limited and the fast neutron fluence accumulated in its service life should not be higher than 1 × 10 18 n cm −2 . This design limit is slightly different from the previous report [5] as the engineering design of CFETR changes. The results of fast neutron fluence and nuclear heating are plotted in figures 9 and 10.…”

Section: Vv and Coilscontrasting

confidence: 77%

“…The nuclear responses of neutron wall loading (NWL), nuclear heating, irradiation damage and TBR have been evaluated here. The shielding effect of the WCCB blanket as a key com- ponent of the TFC has been analyzed and reported in reference [5].…”

Section: Blanketmentioning

confidence: 99%

“…In this paper, the WCCB blanket has been integrated into CFETR to study its neutronic features. Accordingly, its shielding capabilities, focusing of nuclear irradiation loading on the oroidal field coil (TFC) and VV, were evaluated and the shielding design was optimized [4,5]. The heating systems of ECRH, ICRH, LHW and NBI were analyzed for their nuclear responses because they are all nominal plasma-facing components and heavily irradiated by neutrons.…”

Section: Introductionmentioning

confidence: 99%

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Progress on neutronic analysis for CFETR

Lu¹,

Wu²,

Du³

et al. 2022

Nucl. Fusion

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The neutron induced irradiation field is a key problem in fusion reactor related to nuclear responses, shielding design, nuclear safety, and thermo-hydraulic analysis. To support the system design of China Fusion Engineering Test Reactor (CFETR), the comprehensive analysis of irradiation field has been conducted in support of many new developed advanced tools. The paper first summarizes the recent progress on related neutronics code development effort including the geometry conversion tool cosVMPT, Monte Carlo variance reduction technology ‘on-the-fly’ global variance reduction (GVR). Such developed tools have been fully validated and applied on the CFETR nuclear analysis. The neutron irradiation has been evaluated on CFETR Water Cooled Ceramic Breeder (WCCB) blanket, divertor, vacuum vessel, superconductive coils and four kinds of heating systems including the Electron Cyclotron Resonance Heating (ECRH), Ion Cyclotron Resonance Heating (ICRH), Low Hybrid Wave (LHW) and Neutral Beam Injection (NBI). The nuclear responses of tritium breeding ratio (TBR), heating, irradiation damage, Hydrogen/Helium (H/He) production rate of material have been analyzed. In case of neutron damage and overheating deposition on the superconductive coils and Vacuum Vessel (VV), the interface and shielding design among heating systems, blanket and other systems has been initialized. The results show the shielding design can meet the requirement of coil and VV after several iterated neutronics calculation.

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Section: Vv and Coilscontrasting

confidence: 77%

Section: Blanketmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Progress on neutronic analysis for CFETR

Lu¹,

Wu²,

Du³

et al. 2022

Nucl. Fusion

Self Cite

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“…The physics and engineering designs of the CFETR are still under development, starting from phase I, which includes a major/minor radius of 5.7 m/1.6 m and plasma current of 10 MA, towards phase II in pursuit of improving the design and performance by building a larger facility size of R=6.6 m/a=1.8 m [3]. The latest structure of the CFETR was initialized in 2018, with the most recent facility size further increased to R=7.2 m, and fusion power extended from 200 MW, 500 MW and 1 GW to 1.5 GW in just one facility, which will make it more adaptable but more challenging in terms of its engineering design [4].…”

Section: Introductionmentioning

confidence: 99%

“…The damage induced by neutron irradiation could degrade the material characteristics of the system's components. The overall divertor system is unable to offer enough protection to the vacuum vessel (VV) and toroidal field coil (TFC), especially with the latest design features of the CFETR due to the fact that several significant modifications have been adopted, which might cause changes in its neutronics performance [3,4].…”

Section: Introductionmentioning

confidence: 99%

A study on nuclear analysis of the divertor region of the CFETR

Saidahmed

Yao

et al. 2021

Plasma Sci. Technol.

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This paper presents the nuclear analysis performance of the Chinese Fusion Engineering Test Reactor (CFETR) divertor region using the MCNP-5 Monte Carlo N-particles code in a 3D geometry model. We assessed the nuclear responses of the divertor region component systems and evaluated their shielding capability, which can support the development strategy of the physical and engineering design of the CFETR. Model specification based on the latest CAD model of the CFETR divertor has been integrated into the CFETR MCNP reference model with a major/minor radius R=7.2 m/a=2.2 m in the 22.5°model, and a fusion-power range of around 1-1.5 GW. The nuclear heating and radiation damage of the divertor system are enhanced compared to that of the ITER and the earlier CFETR design. The initial nuclear responses of the toroidal field coil and vacuum vessel systems showed that the shielding of the current divertor design is not sufficient and optimization work has been carried out. We also carried out calculations and analysis using a hypothetical operating scenario of over 14 years. An excellent improvement in the nuclear performance has been obtained by the improved additional shielding block in the divertor region when referring to the ITER design limit, which can support the design of the future update of the divertor region systems of the CFETR.

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Operation and shutdown dose rate analysis of CFETR ECRH system

Zhang

et al. 2020

Fusion Engineering and Design

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Analysis of nuclear response in CFETR toroidal field coils with density reduction VR technique

Cited by 7 publications

References 13 publications

Progress on neutronic analysis for CFETR

Progress on neutronic analysis for CFETR

A study on nuclear analysis of the divertor region of the CFETR

Operation and shutdown dose rate analysis of CFETR ECRH system

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