1,721,287 research outputs found
Analisi dello stato dell'arte sul coefficiente di scambio termico con vapore in condensazione nei sistemi di contenimento dei reattori nucleari
No full textThis paper presents a literature review of available analytical works and a survey of recent experiments and current models, relevant to the prediction of condensation heat transfer in a containment building following a postulated accident. Very little information is available with direct applicability to large power reactor containment systems on which to base concrete recommendations
Analysis of the OECD/CSNI ISP No. 46 on the PHEBUS FPT-1 Test Using the ECART 2k Code
Full text linkThis report DIMNP 016 (02) deals with the results of the integrated analyses performed at the “Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione” (DIMNP) of Pisa University (I) on the PHEBUS FPT-1 Test, carried out in the PHEBUS test reactor at CEA Cadarache (F), using the CESI / EdF ECART (ENEL Code for Analysis of Radionuclide Transport) code in its version 2K.
The goal of this test PHEBUS FPT-1 was to investigate the phenomena that play a role in the transport, the physical behaviour and the chemistry of FPs during postulated SAs in a PWR under prototype conditions of irradiated fuel and give an xperimental data set for validation of computer programmes that have been designed to simulate the different stages of a SA sequence.
These activities have been carried out in the framework of the OECD/CSN International Standard Problem (ISP) No. 46 (Phase 2 & 3) and the related European Project THENPHEBISP (Contract FIKS-CT-2001-20151)
Applications of Severe Accidents Codes to the Safety Analysis of the ITER Fusion Reactor
No full textEx-Vessel Break in the ITER Divertor Cooling Loop Using the ECART Code
Full text linkThis work is related to the application of the CESI and Edf ECART code on the analysis of a large ex-vessel break in the divertor cooling loop of the ITER reactor. These activities are carried out in the general framework of the validation phase of the ECART code, initially developed by ENEL and EdF for integrated analysis of severe accidents in LWRs, for its application on incidental sequences related to the ITER fusion plant.
ECART was originally designed and validated for traditional NPP safety analyses and it is internationally recognized as a relevant nuclear source term code for nuclear fission plants. It permits the simulation of chemical reactions and transport of radioactive gases and aerosols under two-phase flow transients in generic flow systems, using a built-in thermal-hydraulic model.
A comparison of the ECART data with the results obtained by NFR Studsvik Nuclear AB (Nyköping, Sweden), utilising the MELCOR code in its fusion version for the same sequence, has been also performed during the present task. This comparison gives a quite good qualitative and quantitative agreement in the results, both for the thermal-hydraulics main parameters and the environmental radioactive releases
PPCS Power Plant Conceptual Study - ECART Analysis of an In-Vessel Break in the First Wall
No full textPresentation of the ECART analysis for an In-Vessel Break in the First Wall of the PPCS Power Plant Conceptual Stud
University of Pisa MELCOR Analysis on TMI-2 scenarios
No full textContribution of Pisa University at the analysis of the OECD/CSNI TMI-2 Benchmarks using the MELCOR computer cod
SAMG objectives and requirements: Methodology and Computer Codes for SA analysis
No full textSOAR and review of the methodologies and computer codes employed for SA analysis having in mind the SAMG objectives and the requirements of a regulato
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