1,720,980 research outputs found

    Development and Validation of the ECART Code for the Safety Analysis of Nuclear Installations

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    ECART can simulate the thermal-hydraulic behavior of LWR and GCR plants under severe accident conditions together with the transport of radiotoxic substances. This tool is still under improvement and assessment for new applications in non-nuclear risk studies, new advanced and fusion reactors. As regards accidents with fires within closed environments, specific models can simulate both thermal and chemical processes, accounting for combustion of gases and solids, as well as pool fires. The radiative heat transfer and the action of water sprays on atmosphere cooling and aerosol removal are properly taken into account, as verified by comparing the code predictions to full-scale experiments and to the consequences of fire accidents really occurred. About its application on tokamak fusion plants, a large validation activity is underway, mainly based on the analyses of ad hoc experimental programs or code benchmark promoted inside EURATOM Fusion Technology Programme. The correct simulation of the main phenomena occurring in ICE and STARDUST facilities, as well as the comparison with the results of codes employed in the fusion safety studies, demonstrates the applicability of ECART models in performing a realistic prediction of the whole incidental sequence, accounting both thermal-hydraulics and dust transport also inside fusion plants

    Assessment and Validation of ECART Code in Support to Severe Accident Radionuclide Transport

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    Presentation of the assessment and validation activities for the ECART Code in support to the studies on radionuclide transport during a severe accident in a LW

    Analysis of an Ex-Vessel Break in the ITER Divertor Cooling Loop with the ECART Code

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    In the frame of the Generic Site Safety Report GSSR for the ITER experimental plant, several accident analyses have been carried out to quantify in detail the radiological risk linked with the possible releases. In this context a hypothetical double-ended pipe rupture of the largest pipe was analysed to bound all possible leaks in the ex-vessel section of a divertor primary heat transfer system during pulse operation. That analysis was performed using a thermal-hydraulic system code, a containment code and an aerosol transportation code. The present paper shows the results obtained by using, for the same accident, only the nuclear source term ECART code. A comparison with the results given in GSSR is also presented and discussed

    Thermal-hydraulic modeling and severe accident radionuclide transport

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    The evaluation of radionuclide transport within a nuclear reactor plant and then to the external environment after an accident that involves severe damage to the fuel rods requires an appropriate evaluation of the thermal-hydraulic conditions that influence both the chemical equilibria among the involved species and the radionuclide retention phenomena. The ENEL Code for the Analysis of Radionuclide Transport (ECART) computer program has been developed for the purpose of unifying reactor cooland and containment system analysis and represents the current state of the art of light water reactor severe accident aerosol codes. New aerosol transport models, like physical resuspension and transport under two-phase flow within the reactor coolant system, are included. The code comprises three modules that deal with aerosol transport, chemical equilibria, and thermal hydraulics, respectively. The recently developed thermal-hydraulic module has been applied to the analysis of transients typically addressed by the code to obtain first indications about the adequacy of the adopted models and about the need for further improvements. A thorough assessment is now needed to achieve confidence in the modeling capabilities of the module. The three modules are presently coupled in the integrated ECART code. The obtained code will be further assessed by application to relevant severe accident scenarios
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