Integrated safety analysis code system (ISAS) application for accident sequence analyses

M.T. Porfiri, G. Cambi

Research output: Contribution to journalArticle

3 Citations (Scopus)

Abstract

In the frame of the ITER Task `Reference Accident Sequences', two accident sequences have been assessed to demonstrate the effectiveness of the use of integrated safety analysis code system (ISAS). The first one is a loss of coolant event in the divertor primary heat transfer system (DV PHTS) towards the vacuum vessel containment during normal plasma burn; the second one is a loss of coolant event in the DV PHTS towards the lower vault during baking conditions. The comparison of the results obtained in standalone and coupled modes was performed. The codes used for the analyses are ATHENA for thermal-hydraulic simulation, INTRA for containment studies and NAUA for aerosol transportation. The three codes are linked together in the ISAS chain by means of files written in the Gibiane language. The ISAS application seems to be promising in order to have a powerful tool in the fusion plant accident analysis. It is able to treat different codes, developed for different fields of applications, as a unique code simulating the complete evolution of an accident sequence. ISAS permits a detailed exchange of data between the codes, otherwise impossible in standalone mode. It reduces the errors in typing exchange data and takes into account the feedback effects during the calculation. The coupling of the codes makes possible to compensate the lack of some phenomenon models in one code if they are treated in another code of the chain (i.e. radiative heat exchange between heat structures that is missing in ATHENA and foreseen in INTRA). The results obtained in the two accident analyses demonstrate that ISAS can be very useful to represent in a more coherent way the trend of an accident respecting the correct balance of the inventories. In the paper the whole evolution of a typical fusion power plant accident is analyzed starting from the break in the cooling loop system, studying the effects of the loss of coolant in the containment and simulating the leakage of the aerosols outside vacuum vessel and vaults.
Original languageEnglish
Pages (from-to)587 - 591
Number of pages5
JournalFusion Engineering and Design
Volume51-52
DOIs
Publication statusPublished - 2000
Externally publishedYes

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All Science Journal Classification (ASJC) codes

  • Civil and Structural Engineering
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Mechanical Engineering

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