Nuclear Energy for New Europe 2009

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No: 216

Conference: Nuclear Energy for New Europe 2009

Title: The Numerical Simulation of the WWER44/V213 Reactor Pressure Vessel Internals Response to Maximum Hypothetical Large Break Loss of Coolant Accident

Theme: Thermal Hydraulics

Author(s): Peter Hermansky, Marian Krajčovič

Contact : Peter Hermansky

E-mail: hermanskyp@vuje.sk

Address: VUJE Trnava, a.s.
918 64 Trnava

Country: Slovak Republic

The reactor internals are designed to ensure cooling of the fuel, to ensure the movement of control rods under all operating conditions including accidents and facilitate removal of the fuel and of the internals following an accident. This paper presents preliminary results of the numerical simulations of the WWER440/V213 reactor vessel internals (RVI) dynamic response to maximum hypothetical Large-Break Loss of Coolant Accident (LBLOCA). In case of this LOCA accident it is assumed rapid “guillotine” break of one of the main coolant pipes and rapid depressurization of the primary circuit. The pressure wave spreads at the speed of sound and enters the reactor pressure vessel and causes deformation and stress in reactor vessel internals.
The purpose of this analysis is to determine reactor pressure vessel internals response, and structural integrity due to rapid depressurization and to prove no permanent (plastic) deformations occur in the RVI which would prevent timely and proper activation of the control rods.
The finite element model was created by MSC.PATRAN and dynamic response was solved using MSC.DYTRAN. The model consists of reactor vessel internals (Lagrangian solid elements) and water coolant (Euler elements). Arbitrary Lagrangian Eulerian coupling was used for simulation of the fluid-structure interaction. The calculation assumes no phase change in the water. Comparison with the experiment was not performed up to now, because required experimental data are not accessible for this type of the reactor.

No:	216
Conference:	Nuclear Energy for New Europe 2009
Title:	The Numerical Simulation of the WWER44/V213 Reactor Pressure Vessel Internals Response to Maximum Hypothetical Large Break Loss of Coolant Accident
Theme:	Thermal Hydraulics
Author(s):	Peter Hermansky, Marian Krajčovič
Contact :	Peter Hermansky
E-mail:	hermanskyp@vuje.sk
Address:	VUJE Trnava, a.s. 918 64 Trnava
Country:	Slovak Republic

The reactor internals are designed to ensure cooling of the fuel, to ensure the movement of control rods under all operating conditions including accidents and facilitate removal of the fuel and of the internals following an accident. This paper presents preliminary results of the numerical simulations of the WWER440/V213 reactor vessel internals (RVI) dynamic response to maximum hypothetical Large-Break Loss of Coolant Accident (LBLOCA). In case of this LOCA accident it is assumed rapid “guillotine” break of one of the main coolant pipes and rapid depressurization of the primary circuit. The pressure wave spreads at the speed of sound and enters the reactor pressure vessel and causes deformation and stress in reactor vessel internals. The purpose of this analysis is to determine reactor pressure vessel internals response, and structural integrity due to rapid depressurization and to prove no permanent (plastic) deformations occur in the RVI which would prevent timely and proper activation of the control rods. The finite element model was created by MSC.PATRAN and dynamic response was solved using MSC.DYTRAN. The model consists of reactor vessel internals (Lagrangian solid elements) and water coolant (Euler elements). Arbitrary Lagrangian Eulerian coupling was used for simulation of the fluid-structure interaction. The calculation assumes no phase change in the water. Comparison with the experiment was not performed up to now, because required experimental data are not accessible for this type of the reactor.