Tritium and heat management in ITER Test Blanket Systems port cell for maintenance operations

Giancarli, L.; Cortes, Pierre; Iseli, Markus; Lepetit, L.; Levesy, B.; Livingston, Drake; Nevière, J.-C.; Romain, P.; Ricapito, I.; Shu, W.M.; Wyse, S.

doi:10.1016/j.fusengdes.2014.01.059

Cited by 10 publications

(6 citation statements)

References 3 publications

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“…Temperature is also an essential factor affecting the transport of HTO in both air and walls [24,25]. The predicted heat source of 11 kW is lower than the Local Air Cooling (LAC) design value of 43 kW [7]. Thus, the thermal distribution in the TBM port cell remains stable and fluctuates around room…”

Section: Methodsmentioning

confidence: 99%

“…A steady-state flow field would be established after the DS functioned for a while. The detritiation outlet boundary condition was set to 40 m 3 h −1 , while the inlet was set to −100 Pa to ensure a negative pressure environment in the plant [7]. Figure 2 illustrates the steady-state flow field in the TBM port cell.…”

Section: Steady-state Flow Fieldmentioning

confidence: 99%

“…In 2014, Giancarli et al delineated an analytical approach to assess tritium concentration variation in port cell after the plasma shutdown [7]. A good compromise to reach the target that tritium concentration in air reduce to 1 DAC in less than 12 h is given by the case with 40 m 3 h −1 at normal DS and 60 m 3 h −1 for enhanced DS.…”

Section: Introductionmentioning

confidence: 99%

“…All the tritium management is based on 0/1 D models or analytical methods [7][8][9][10][11][12], which cannot obtain the accurate distribution of tritium if there is ample space with a complex flow field. Besides, the tritium from TBS makes an HTO environment in the port cell plant.…”

Section: Introductionmentioning

confidence: 99%

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Tritium management in ITER test blanket systems port cell for maintenance operations

Jiang,

Wu,

et al. 2024

Nucl. Fusion

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Four Test Blanket Systems (TBS) will be tested in the International Thermonuclear Experimental Reactor (ITER) equatorial ports #16 and #18 to verify tritium breeding and heat extraction technology. A significant quantity of tritium would be produced in TBM, and partly released into the port cell from the pipework of TBS or other high-temperature components due to its strong mobility and high permeation. The port cell should be accessible during equipment maintenance and human intervention. This work built a multi-dimensional geometric model to characterize HTO transport in the port cell, absorption/desorption, and diffusion in walls and discussed the effect of paint thickness, ventilation rate, source term, and epoxy properties on detritiation efficiency. The results suggest that a 0.1-0.16 mm paint with the lowest HTO solubility is optimal from the compromise between quick cleanup and tritiated waste decommission. A higher ventilation rate could accelerate detritiation while minimizing the radioactive source by a tritium-resisting layer is the most direct method. The optimized design options for reducing the time required to reach 1 DAC in 12 h still need further discussion because of the delayed HTO source from epoxy paint and dead zone of the flow field.

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Section: Methodsmentioning

confidence: 99%

Section: Steady-state Flow Fieldmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Tritium management in ITER test blanket systems port cell for maintenance operations

Jiang,

Wu,

et al. 2024

Nucl. Fusion

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“…Vītiņš et al considered the relationship between tritium release and material temperature in the blanket design for the ITER and DEMO reactors [16]. In addition, Giancarli et al said that an ITER organization test blanket module (TBM) should be carried out for 'tritium and heat management' in blanket module temperature control [17]. All these cases indicate that tritium production inside the blanket system has a direct relation to the TCM.…”

mentioning

confidence: 99%

Study on the temperature control mechanism of the tritium breeding blanket for CFETR

et al. 2017

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The Chinese fusion engineering testing reactor (CFETR) will demonstrate tritium self- sufficiency using a tritium breeding blanket for the tritium fuel cycle. The temperature control mechanism (TCM) involves the tritium production of the breeding blanket and has an impact on tritium self-sufficiency. In this letter, the CFETR tritium target is addressed according to its missions. TCM research on the neutronics and thermal hydraulics issues for the CFETR blanket is presented. The key concerns regarding the blanket design for tritium production under temperature field control are depicted. A systematic theory on the TCM is established based on a multiplier blanket model. In particular, a closed-loop method is developed for the mechanism with universal function solutions, which is employed in the CFETR blanket design activity for tritium production. A tritium accumulation phenomenon is found close to the coolant in the blanket interior, which has a very important impact on current blanket concepts using water coolant inside the blanket. In addition, an optimal tritium breeding ratio (TBR) method based on the TCM is proposed, combined with thermal hydraulics and finite element technology. Meanwhile, the energy gain factor is adopted to estimate neutron heat deposition, which is a key parameter relating to the blanket TBR calculations, considering the structural factors. This work will benefit breeding blanket engineering for the CFETR reactor in the future.

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Innovations in Technology and Science R&D for ITER

et al. 2019

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Tritium and heat management in ITER Test Blanket Systems port cell for maintenance operations

Cited by 10 publications

References 3 publications

Tritium management in ITER test blanket systems port cell for maintenance operations

Tritium management in ITER test blanket systems port cell for maintenance operations

Study on the temperature control mechanism of the tritium breeding blanket for CFETR

Innovations in Technology and Science R&D for ITER

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