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Modelling of Ingress of Coolant Event into Vacuum Experiments with ASTEC Code

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Abstract

Accident analysis of fusion facilities is important part of safety assessment. Validated computer codes are required to perform such analysis. At present ASTEC code is being actively developed by IRSN to include features required for safety analysis of fusion facilities. This paper presents detailed analysis of P1 test performed at ICE test facility using CPA module of ASTEC code. Results of performed analysis confirmed that ASTEC could be successfully applied for analysis of loss of coolant accidents in fusion facilities like ITER or W7-X. Modelling of the pressure suppression system included in ASTEC is adequate as well. Peculiar gas compression effect was observed in the drain tank. This compression effect and gas temperature behaviour could be further investigated to resolve remaining issues.

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Authors and Affiliations

  1. Laboratory of Nuclear Installation Safety, Lithuanian Energy Institute, Breslaujos g. 3, 44403, Kaunas, Lithuania

    Tomas Kačegavičius & Egidijus Urbonavičius

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  1. Tomas Kačegavičius
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  2. Egidijus Urbonavičius
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Correspondence to Tomas Kačegavičius.

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Kačegavičius, T., Urbonavičius, E. Modelling of Ingress of Coolant Event into Vacuum Experiments with ASTEC Code. J Fusion Energ 34, 320–325 (2015). https://doi.org/10.1007/s10894-014-9804-4

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  • DOI: https://doi.org/10.1007/s10894-014-9804-4

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