Izvestia Vysshikh Uchebnykh Zawedeniy. Yadernaya Energetika

The peer-reviewed scientific and technology journal. ISSN: 0204-3327

Study of regimes with disturbance of the conditions of cooling the reactor plant from the side of the secondary circuit of reactor VVER

10/02/2016 2016 - #03 Modelling processes at nuclear facilities

Belozerov V.I. Botko E.N. Zhuk M.M.

UDC: 621.039.586

Heathydraulic calculations are a necessary component of the majority of design and technological development in nuclear power. As in the conditions of the NPP the way of check, traditional for equipment, and specification of results and conclusions of the aprioristic analysis on the basis of industrial tests can’t be realized, in some cases means of research and the forecast of parameters of heathydraulic processes in a circulating contour of the reactor are researches with application of heathydraulic program codes.

Calculation and study of regimes with the disturbance of the conditions of cooling the reactor plant from the side of secondary circuit with the reactor VVER is placed with basic task in the work, using the computer program codes, for the purpose of the determination of the correspondence of the calculated parameters by the established normative documentation to reception criteria.

On the base of the program codes RELAP-5, TRAC, TRACE were modelled and investigated the regimes of the work of reactor plant with the disturbance of cooling conditions from the side of the secondary circuit of reactor VVER#1000.v to article they were given the results of the analysis of regime with closing of the check valves of turbogenerator. The dependences obtained they made it possible to determine the maximum values of pressures and temperatures in the circulation loop, and to also estimate minimum reserves to the crisis of heat exchange. As a result established that with the appearance of each of the initial events occurs the wear and tear of security systems according to settings, transient processes are stabilized in the time, reserve to the crisis of boiling on the shells FUEL ELEMENT is ensured. Consequently, in the case of the not on the staff situation, connected with in question in the work regimes, the safety of reactor plant will be provide ford.


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regime disturbance of heat with drawal reactor plant pressure stop valve crisis of boiling stock coefficient