Hydrogen recycling and its control on HL-1 tokamak

Peng, Li‐Yan; Yan, Chengjie; Cao, Z.; Keqiang, Huang; Zheng, Y.Z.; Shangjie, Qian; Luo, Junhua

doi:10.1016/s0022-3115(06)80091-7

Cited by 7 publications

(3 citation statements)

References 4 publications

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“…After tokamak discharges, the hydrogen retention in the form of H + is higher. The inert gas helium GDC is helpful in depleting this kind of hydrogen retention [18].…”

Section: Hydrogen Retentionmentioning

confidence: 99%

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Improvement of plasma performance with wall conditioning in the HL-1M tokamak

et al. 1998

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Studies and selection of plasma facing materials continue to be a concern for future fusion devices, and ongoing efforts are being made in the HL-1M tokamak. The advanced methods of wall modification adopted on HL-1M are surveyed. Significant improvements in tokamak plasma performance have been obtained by using boron, silicon or lithium containing substances as a material for wall coatings. The siliconization technique is highlighted. Lithiumization, as the newest technique, will be investigated further.

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“…After tokamak discharges, the hydrogen retention in the form of H + is higher. The inert gas helium GDC is helpful in depleting this kind of hydrogen retention [18].…”

Section: Hydrogen Retentionmentioning

confidence: 99%

“…38, No. 8 (1998) wall leads to strong wall fuelling [18]. The oxygen is still the dominant light impurity together with the low-Z element carbon.…”

Section: Introductionmentioning

confidence: 99%

Improvement of plasma performance with wall conditioning in the HL-1M tokamak

et al. 1998

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“…We can operate D-T burning and D-D 'sponge effect' discharge alternately in the process. The deactivation time of the'sponge effect' depends on the total number of trapped deuterium atoms in the materials, deuterium re-deposition, tritium desorption by the impinging particles [10], wall temperature, integral fast neutral atom flux produced by charge exchange to the wall surface from the plasma, fuelling rate, integral total effective D-T burn time, plasma burn-up fraction, PFC material type and edge plasma conditions, etc.…”

Section: 'Sponge Effect' For Reducing Tritium Retentionmentioning

confidence: 99%

Tritium well depth, tritium well time and sponge mechanism for reducing tritium retention

Deng

et al. 2011

Nucl. Fusion

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New simulation results are predicted in a fusion reactor operation process. They are somewhat similar to, but quite different from, the xenon poisoning effects resulting from fission-produced iodine during the restart-up process of a fission reactor. We obtained completely new results of tritium well depth and tritium well time in magnetic confinement fusion energy research area. This study is carried out to investigate the following: what will be the least amount of tritium storage required to start up a fusion reactor and how long the fusion reactor needs to be operated for achieving the tritium break-even during the initial start-up phase due to the finite tritium-breeding time, which is dependent on the tritium breeder, specific structure of the breeding zone, layout of the coolant flow pipes, tritium recovery scheme and applied extraction process, the tritium retention of plasma facing component (PFC) and other reactor components, unrecoverable tritium fraction in the breeder, leakage to the inertial gas container and the natural radioactive decay time constant. We describe these new issues and answer these problems by setting up and solving a set of equations, which are described by a dynamic subsystem model of tritium inventory evolution in a fusion experimental breeder (FEB). Reasonable results are obtained using our simulation model. It is found that the tritium well depth is about 0.319 kg and the tritium well time is approximately 235 full power operation days for the reference case of the designed FEB configuration, and it is also found that after one-year operation the tritium storage reaches 0.767 kg, which is more than the least amount of tritium storage required to start up another FEB-like fusion reactor. The results show that the tritium retention in the PFC is equivalent to 11.9% of tritium well depth that is fairly consistent with the result of 10–20% deduced from the integrated particle balance of European tokamaks. Based on our experimental and theoretical studies, some new mechanisms are proposed for reducing the tritium retention in PFC and structure materials of tritium-breeding blanket. In this paper, a qualitative analysis of the ‘sponge effect’ is carried out. The ‘sponge effect’ may help us to reduce tritium retention by ∼20% in the PFC.

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Literature mapping of waste sorting and recycling behavior research: a visual analysis using CiteSpace

Yang

Zhang

2023

Environ Sci Pollut Res

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Hydrogen recycling and its control on HL-1 tokamak

Cited by 7 publications

References 4 publications

Improvement of plasma performance with wall conditioning in the HL-1M tokamak

Improvement of plasma performance with wall conditioning in the HL-1M tokamak

Tritium well depth, tritium well time and sponge mechanism for reducing tritium retention

Literature mapping of waste sorting and recycling behavior research: a visual analysis using CiteSpace

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