Design of the ITER–FEAT cryoplant to achieve stable operation over a wide range of experimental parameters and operation scenarios

Claudet, G.; Kalinine, V.; Mitchell, N.; Roussel, P.; Shatil, N.

doi:10.1016/s0920-3796(01)00434-3

Cited by 13 publications

(6 citation statements)

References 3 publications

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“…and the choke for mechanical soundness and stable operation. Therefore, it is important to understand the performance of the cold compressors for the reliable operation of the cooling system, especially the transient characteristics against large disturbance due to heat load generated in superconducting coils [10][11][12][13]. In the present study, the thermal hydraulic behavior of the helium subcooling system and the operational performance during ten plasma experimental campaigns are reported.…”

Section: Fig 1 Photograph Of the Large Helical Device (Lhd) Which Ismentioning

confidence: 99%

Operations of the Helium Subcooling System for the LHD Helical Coils during Ten Plasma Experimental Campaigns

Hamaguchi

Imagawa

Obana

et al. 2018

Plasma and Fusion Research

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The Large Helical Device has a helium subcooling system with two cold compressors for helical coils to enhance the magnetic fields and improve the cryogenic stability of the coils by lowering the coil temperature. The system was installed in 2006 and then it has stably supplied 3.2 K subcooled helium at the nominal mass flow rate of 50 g/s to the coils during ten plasma experimental campaigns. The running time of the cold compressors exceeds 30,000 hours and the total time of subcooling operations exceeds 20,000 hours. In the system, the supplied helium is subcooled in a heat exchanger of a saturated helium bath. The bath pressure and temperature are reduced by a series of two centrifugal cold compressors with gas foil bearing. In the steady state subcooling operation, the bath temperature is stabilized within range of 0.02 K with automatic flow control of helium gas through the cold compressors by a heater in the bath. The control method is also useful to protect the system by mitigating large disturbance of the pressure and the mass flow rate. In the present study, the thermal hydraulic behavior of the system and the operational performance during ten plasma experimental campaigns are reported.

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Section: Fig 1 Photograph Of the Large Helical Device (Lhd) Which Ismentioning

confidence: 99%

Operations of the Helium Subcooling System for the LHD Helical Coils during Ten Plasma Experimental Campaigns

Hamaguchi

Imagawa

Obana

et al. 2018

Plasma and Fusion Research

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“…The minimum flow capacities of the pumps and hence the minimum heat load on the LHe plant are obtained on the basis of the 1D, 2D and quasi-3D Vincenta numerical cooling models [1,2]. These models enable investigation of the detailed temperature profiles in the coils and structures taking into account nonuniform (in space and time) distribution of the electromagnetic heat losses and nuclear heat load.…”

Section: Cryo-distribution Boxesmentioning

confidence: 99%

“…A special cooling procedure has been developed [2][3][4] for allowing active smoothing of the pulsed heat load. A bypass valve is included in each ACB, as shown in Fig.…”

Section: Mitigation Of Pulsed Heat Loadsmentioning

confidence: 99%

ITER cryogenic system

Kalinin¹,

Tada²,

Millet

et al. 2006

Fusion Engineering and Design

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“…The key design requirement of the CFETR cryogenic system is to withstand the large pulsed heat loads deposited in the magnets due to the magnetic field variation and the neutron production from deuterium-tritium (D-T) fusion reaction [6][7][8].…”

Section: Introductionmentioning

confidence: 99%

Conceptual design of the cryogenic system and estimation of the recirculated power for CFETR

Liu

Qiu

et al. 2016

Nucl. Fusion

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The China Fusion Engineering Test Reactor (CFETR) is the next tokamak in China’s roadmap for realizing commercial fusion energy. The CFETR cryogenic system is crucial to creating and maintaining operational conditions for its superconducting magnet system and thermal shields. The preliminary conceptual design of the CFETR cryogenic system has been carried out with reference to that of ITER. It will provide an average capacity of 75 to 80 kW at 4.5 K and a peak capacity of 1300 kW at 80 K. The electric power consumption of the cryogenic system is estimated to be 24 MW, and the gross building area is about 7000 m2. The relationships among the auxiliary power consumed by the cryogenic system, the fusion power gain and the recirculated power of CFETR are discussed, with the suggestion that about 52% of the electric power produced by CFETR in phase II must be recirculated to run the fusion test reactor.

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Design of the ITER–FEAT cryoplant to achieve stable operation over a wide range of experimental parameters and operation scenarios

Cited by 13 publications

References 3 publications

Operations of the Helium Subcooling System for the LHD Helical Coils during Ten Plasma Experimental Campaigns

Operations of the Helium Subcooling System for the LHD Helical Coils during Ten Plasma Experimental Campaigns

ITER cryogenic system

Conceptual design of the cryogenic system and estimation of the recirculated power for CFETR

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