Optimization of the ITER Cryodistribution for an Efficient Cooling of the Magnet System

Chang, Hyuk; Maekawa, R.; Forgeas, A.; Clough, M.; Vaghela, Hitensinh; Bhattacharya, R.; Sarkar, B.

doi:10.1109/tasc.2016.2517940

Cited by 9 publications

(4 citation statements)

References 6 publications

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“…The pulsed heat load in fusion device is more relevant for the tokamak based magnetic confinement fusion devices since the current in the plasma is induced by the current swing in a central solenoid, which also induces eddy currents (and hence heat load) in SC Magnets. Broadly, two methods are being utilized for smoothening of pulsed heat load, viz., the application of thermal damper using a sizable LHe bath with buffer volume [ 12 ] and/or utilizing the thermal inertia of the huge mass of SC magnet structure [ 32 , 33 , 34 ]. The peak heat load is temporarily absorbed in the thermal damper (in the first case) and then released to the low-pressure side of helium R/L during the dwell period.…”

Section: Cryogenic System In Fusion Devicesmentioning

confidence: 99%

Forced flow cryogenic cooling in fusion devices: A review

Vaghela

Lakhera

Sarkar

2021

Heliyon

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The constantly increasing energy consumption along with the depleting fossil fuel resources as well as owing to the fact that the nuclear fission not being an intrinsically safe method of energy generation, it has become necessary to look for other solutions to fulfil the future energy demands. Nuclear fusion, the source of energy for billions of stars, has attracted the attention of scientists and engineers despite a lot of technical challenges in the replication of the fusion process in laboratories. For fusion to take place in a device, one of the major challenges faced is the strong magnetic confinement of the plasma using large superconducting (SC) magnets, which need efficient cryogenic cooling techniques to maintain the required low temperatures for the superconducting state. In order to maintain the compactness, the SC magnets generally employ Cable in Conduit Conductor (CICC) windings, carrying high current densities, which are cooled by the forced flow of helium at ~4 K temperature to maintain the required superconducting temperatures. The construction of CICC aims to maintain the superconductivity state by optimization of various parameters such as thermal stability, the ratio of normal conductor to SC material, mechanical strength, low hydraulic impedance, current density, magnetic field, etc. The cryogenic thermal stability of the CICC is of prime importance for safe, stable and reliable operation of SC magnets. The prediction of thermal and hydraulic behavior of the CICC in large SC magnets is difficult due to the complex geometry involved, the variation in fluid properties, various heat in-flux incidences over the long length of CICC and a complex heat transport phenomenon. Another application which utilizes a forced flow cryogenic cooling in the fusion devices is a cryo-adsorption pump for creating clean and high vacuum with large pumping speed. This paper presents an overview of the forced flow cryogenic cooling schemes in fusion devices along with a systematic review of the thermal and hydraulic studies related to CICC and cryo-adsorption pump, thereby highlighting the challenges and opportunities for further improvement in their design and performance.

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Section: Cryogenic System In Fusion Devicesmentioning

confidence: 99%

Forced flow cryogenic cooling in fusion devices: A review

Vaghela

Lakhera

Sarkar

2021

Heliyon

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“…As explained in [4], in order to allocate more cooling power to the magnet system, an arrangement with its own CCP (allowing to remove the CCB) and double PS configuration (instead of single PS in [3]) has been selected for all ACBs. A typical internal component configuration is shown in figure 3 for ACB-4 (PF&CC).…”

Section: Optimizations Of the Auxiliary Cold Box Configurationmentioning

confidence: 99%

“…The increase of nuclear heat load during the plasma experiments in some of the SC magnet subsystems required the ACBs to be modified for more flexible and economical operation from the cooling power point of view [4]. Even though it resulted in a more complicated internal arrangement with additional components, the existing Cold Compressor Box (CCB) [3,5] could be removed which allowed the standardization of the ACB component configuration.…”

Section: Introductionmentioning

confidence: 99%

Status of the ITER Cryodistribution

Chang

Vaghela

Patel

et al. 2017

IOP Conf. Ser.: Mater. Sci. Eng.

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Abstract. Since the conceptual design of the ITER Cryodistribution many modifications have been applied due to both system optimization and improved knowledge of the clients' requirements. Process optimizations in the Cryoplant resulted in component simplifications whereas increased heat load in some of the superconducting magnet systems required more complicated process configuration but also the removal of a cold box was possible due to component arrangement standardization. Another cold box, planned for redundancy, has been removed due to the Tokamak in-Cryostat piping layout modification. In this proceeding we will summarize the present design status and component configuration of the ITER Cryodistribution with all changes implemented which aim at process optimization and simplification as well as operational reliability, stability and flexibility.

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“…However, for any one of the coils, the inlet temperature of the SHe can be further lowered to 3.8 K to accommodate conductor and physics requirements [25], and to allow the capability of withstanding possible operation faults or design/ analysis errors [14]. For example, as reported in [26], due to the calculated nuclear heat load during the 400 s burning being drastically increased from 14.4 kW to 28.4 kW, an optim ization of the ITER cryodistribution system is proposed to cool the TF and PF&CC to 3.8 K. This optimization is adopted as shown in the distribution system of figure 3; by individually controlling the bath temperature with a dedicated cold compressor for each of the LHe baths, enhanced cooling at 3.8 K can be concentrated to any one of the coils in need.…”

Section: Conceptual Design Of the Cfetr Cryogenic Systemmentioning

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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Optimization of the ITER Cryodistribution for an Efficient Cooling of the Magnet System

Cited by 9 publications

References 6 publications

Forced flow cryogenic cooling in fusion devices: A review

Forced flow cryogenic cooling in fusion devices: A review

Status of the ITER Cryodistribution

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

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