Complex modeling of VVER-1000 using MCU-Athlet-Flowvision

Document typeConference report
Defense date2017
PublisherCIMNE
Rights accessOpen Access
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property rights. Without prejudice to any existing legal exemptions, reproduction, distribution, public
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Abstract
Nowadays modelling of physical processes is very spread in all fields of physics.
It is possible because of high capacity of computing powers and capability of parallel
computing. We can observe a trend to more detailed description of simulated systems and growth of
calculation schemes complexity. Scientists understand that the feedback of related physical
processes occurring simultaneously could have significant impact on the results of modelling and
should be solved in the scope of multiphysics. That kind of problems exists in reactor physics.
It is vital to perform complex modelling of processes occurring in a fuel core of a nuclear
reactor, especially during the design of the next generation nuclear power plants. It is
not possible to justify safety of the power reactor without complex calculations. In this paper,
we proposed a test case for precise coupled neutronics-thermal hydraulics calculation of VVER-1000
reactor using MCU, ATHLET and FLOWVISION codes. MCU is a general-purpose stochastic
neutron-physical code based on the Monte-Carlo method and characterized by large time of
calculation, as well as CFD codes. Because of that system code ATHLET was used as a fast thermal
hydraulic solver in the iterative scheme. In the end of the calculation we propose to use CFD code
FLOWVISION in order to enhance the precision and verify CFD model for the further complication of
the geometry. The obtained results showed oscillations of power and fuel temperature profiles.
Detailed discussion is given in the article. It is assumed that the test case will be used for
simulation of VVER-1000 reactor in accident–related regimes and for codes cross–verification. The
obtained experience and developed coupling program (PERL script) will be used to create coupled
schemes for complex modelling of
generation IV nuclear reactors involving different computer codes.
ISBN978-84-946909-2-1
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