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Content archived on 2022-12-23

Mathematical simulation of developing nuclear power plant anticipated accident and potential measures for avoiding environment catastrophe

Objective



The heavy failure nuclear reactor vessel, connected with melting of active zone and formation on bottom of reactor vessel corium as kind of liquid-solid medium with internal energy extraction is considered hypotheticality. The thermomechanics problem of interaction corium and reactor vessel is investigated when controlled external cooling. The purpose of project consists: In development of new mathematical models of thermal and mechanical condition corium and metal of reactor vessel; In mathematical realization of these models on bases of advanced numerical methods with subsequent optimization of regimes of external cooling of reactor vessel, enabling to keep corium inside reactor vessel.
The mathematical model of deforming, destruction and melting of reactor bottom is formulated on the basis of equations of condition for nonlinear elasto-viscoplastic body with damages, accrued as a result of high-temperature creep. The processes of melting and solidification are described by theory of nonequilibrum biphase zone of alloys. The development of mechanical destruction is described by moving rupture fronts in view of large creep deformations and deformations of neutron radiation fluency.
The mathematical model of corium is formulated on the basis of equations of condition of liquid-solid medium with internal sources is warm, intensive natural convection and stratified density, temperature and structure. The model of corium solidification is considered and the characteristics of deformability and strength of corium crust are determined. The heat and mass transfer problem in system the corium - reactor vessel and problem of deforming and destruction of reactor bottom are being solved in common by finite element method with sampling and volume digitization.
The result of scientific research under the project is a original computer programs on modeling of a reactor vessel and corium condition under severe accident.

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Funding Scheme

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Coordinator

Institut National Polytechnique de Grenoble
EU contribution
No data
Address

38042 St Martin d'Heres
France

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Total cost

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Participants (1)

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