Preliminary structural design and thermo-mechanical analysis of helium cooled solid breeder blanket for Chinese Fusion Engineering Test Reactor

Li, Min; Chen, Hongli; Zhou, Guangming; Liu, Qianwen; Wang, Shuai; Lv, Zhongliang; Ye, Minyou

doi:10.1016/j.fusengdes.2014.12.011

Cited by 28 publications

(7 citation statements)

References 6 publications

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“…For the “radial‐toroidal‐radial” scheme, the quantity of coolant channels division is larger. This will make both the design and the manufacture of helium manifold more difficult, and may results in the non‐uniform distribution of coolant flow more easily 21,24,25 . However, for the “radial‐poloidal‐radial” scheme, the design and manufacture of helium manifold is relatively easier and the non‐uniform distribution of coolant flow is difficult to arise.…”

Section: Design Scheme Of the Cfetr Phase II Hccb Blanketmentioning

confidence: 99%

“…Up to now, there are several research institutes which have conducted extensive conceptual designs as well as comprehensive analysis and optimization works for CFETR Phase I HCCB blanket 10‐22 . However, in 2018, the operation phase of CFETR has transformed from Phase I to Phase II, and the previous small machine (major radius is 5.7 m, minor radius is 1.6 m) was changed into a larger machine (major radius is 7.2 m, minor radius is 2.2 m) 2,23 .…”

Section: Introductionmentioning

confidence: 99%

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Preliminary design and analyses of the helium cooled ceramic breeder blanket for CFETR phase II

et al. 2020

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Summary China Fusion Engineering Test Reactor (CFETR) has two operation phases: Phase I with Pf = 200 MW is to demonstrate the steady‐state operation; Phase II with Pf = 1 GW is to validate the DEMO technology. Helium Cooled Ceramic Breeder (HCCB) blanket is one blanket candidate for CFETR, and several research institutes have conducted extensive conceptual designs and comprehensive analysis works for Phase I HCCB blanket. However, because the operation phase of CFETR has transformed from Phase I to Phase II and the latest physical design parameters have been just determined, the design and analysis works for HCCB blanket should be initialized. In this work, first, the basic structure design of CFETR Phase II HCCB blanket is performed and a design scheme is proposed according to the design principles and requirements of blanket. Besides, the material selection of each blanket component has been determined. Second, based on the global neutronics model of CFETR Phase II, the neutron wall loadings (NWL) on different blanket modules are calculated. Afterwards, the radial structure layout optimizations of all poloidal blanket modules arranged in a 22.5° toroidal sector are conducted by NTCOC. As for Phase II blanket, which operates under the high fusion power condition, it should be noted that a dynamic feedback is incorporated into the original one‐way optimization method for solving the problems of inadequately optimized tritium breeding performance and insufficient tritium releasing ability. Finally, the radial structure layout parameters of all blanket modules in CFETR Phase II neutronics model are set as the obtained final optimal schemes. The calculation results show that the global TBR of CFETR Phase II is 1.182, which can well meet the tritium self‐sustaining requirement. This work can provide worthy guidance and reference for further conceptual design, comprehensive analyses and optimizations of the CFETR Phase II HCCB blanket.

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Section: Design Scheme Of the Cfetr Phase II Hccb Blanketmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Preliminary design and analyses of the helium cooled ceramic breeder blanket for CFETR phase II

et al. 2020

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“…Thus the average increase of 10 % steel content in FW could cause the TBR reduction rate with about 1.4 %. According to the current thermal-mechanical analysis, it has shown that the current blanket scheme can basically meet the design requirement [12,13], and the sensitivity analysis of the FW modification can be used as a reference for the FW improvements.…”

Section: Effect Of the First Wall Thickness And Steel Content On Tbrmentioning

confidence: 99%

“…1) [5,13]. Because the cooling plate must contain the helium coolant channels to remove the heat deposited in the blanket, the steel content in CP should not be too high.…”

Section: Impact Of Different Thickness Of Cooling Plate On Tbrmentioning

confidence: 99%

Impact Analysis of Helium Cooled Solid Blanket Structures on the Tritium Breeding Performance in CFETR

Zeng

et al. 2016

J Fusion Energ

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Chinese Fusion Engineering Test Reactor (CFETR) is a test tokamak reactor to bridge the gap between ITER and future fusion power plant. As its objectives are to demonstrate generation of fusion power and to realize tritium self-sufficiency, the tritium breeding ratio (TBR) is a key design parameter. In the blanket design and optimization, the structures such as the first wall (FW), cooling plate (CP), stiffening plate (SP), cap and some other design parameters in detailed 3-D model have significant impacts on the tritium breeding performance. Based on a helium cooled solid breeder blanket option for CFETR, the impact analysis of the helium cooled solid blanket structures on tritium breeding performance was performed in this paper. Firstly, the detailed 3D neutronics model was built by using of a CAD to Monte Carlo Geometry conversion tool McCad. Then based on the detailed 3D neutronics model, the impact analyses of the blanket structures on tritium breeding performance were carried out, which include the FW, CP, SP, cap and side wall. By the sensitivity study of the blanket structures on the TBR, it gave the TBR variation trend and references for the blanket design and optimization.

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“…Recently, research on fusion reactors is being conducted around the world. For example, the Chinese Fusion Engineering Test Reactor (CFETR) was designed to demonstrate 50-200 MW fusion power, 30-50% duty cycle, and high tritium breeding ratio (TBR) (Li et al, 2015). The design of fusion blanket is one of the most important components in CFETR, and the helium cooled solid breeder blanket is considered to be the most promising design among several blanket module concepts (Wang et al, 2018).…”

Section: Introductionmentioning

confidence: 99%

Transient heat transfer of helium gas for forced convective flow through a narrow tube with different lengths

SUZUO,

LIU,

SHIBAHARA

2024

Mechanical Engineering Journal

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The understanding of the heat transfer process for helium gas cooling in the fusion blanket is important for the development of fusion reactors. This research aims at clarifying the transient heat transfer characteristics of helium gas for turbulent flow in a narrow tube. A circular platinum tube with an inner diameter of 1.8 mm was heated by exponentially increasing heat inputs and cooled by helium gas. The lengths of the tube were 30 mm and 50 mm. The heat transfer coefficients gradually increased for the e-folding time shorter than about 1.5 s. This shows that the heat transfer process is in a transient state for this region. The heat transfer coefficients increased with the increase of flow velocity, and the effect of the flow velocity became weak in the transient state region. By comparing with the experimental results of tube with different lengths, it was obtained that the quasi-steady state heat transfer coefficients for the length of 30 mm were higher than those for the lengths of 50 mm and 90 mm. However, the heated length showed a weak influence for the lengths of 30 mm and 50 mm in the transient heat transfer with a relatively smaller e-folding time. The variation of transient Nusselt number with Fourier number at different Reynolds number describes well the trend for the variation of heat transfer coefficient with e-folding time at different velocities. Based on the experimental data, an empirical correlation was obtained for transient heat transfer at different lengths by using Fourier number.

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Preliminary structural design and thermo-mechanical analysis of helium cooled solid breeder blanket for Chinese Fusion Engineering Test Reactor

Cited by 28 publications

References 6 publications

Preliminary design and analyses of the helium cooled ceramic breeder blanket for CFETR phase II

Preliminary design and analyses of the helium cooled ceramic breeder blanket for CFETR phase II

Impact Analysis of Helium Cooled Solid Blanket Structures on the Tritium Breeding Performance in CFETR

Transient heat transfer of helium gas for forced convective flow through a narrow tube with different lengths

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