Containment behaviour plays a key role in the safety framework of a Nuclear Power Plant. The GOTHIC thermal hydraulic code has been adopted to evaluate the Atucha-1 NPP containment responses during two postulated accident scenarios, Station Black Out and Large Break Loss of Coolant Accident, while assuming the external cooling of the Reactor Pressure Vessel is carried out during the transients. The Atucha-1 NPP has a containment designed to work at full pressure, constituted by a steel sphere enveloped by a concrete shell, and having an annular gap of air in between. The target of the analysis is the evaluation of the effects caused by the additional production of steam in the reactor cavity as a consequence of the ex-vessel cooling, which could cause an excessive pressurization of the containment, and lead to pressure values above the safety limit. The containment pressure and temperature, the distribution of hydrogen in the containment atmosphere and the water hold-up in the most relevant rooms have been monitored as target variables. Each accident scenario was simulated using two different nodalizations, characterized by a different level of refinement. The "detailed" nodalization is meant to be the most refined nodalization according to the available computational resources; having high fidelity three dimensional details, with a high number cells. While the "coarse" nodalization was developed in order to lower the demand for computational resources without significantly compromising the global scenario response. Both nodalizations are characterized by high complexity in the representation of rooms and their connections, e.g. all doors and blow off panels have been simulated to open with the designed differential pressure logic. Both accident transients, for each type of nodalization, were simulated for 200,000 seconds. Results showed that for the Large Break Loss of Coolant Accident pressure is predicted to reach around 5.25 bar, while the Station Black Out Scenario reaches 4.4 bar.

ATUCHA-1 NPP CONTAINMENT VENTING ANALYSIS FOLLOWING SBO AND LBLOCA EVENTS BY GOTHIC CODE

Alexandru Pop
Primo
;
Walter Giannotti;Fulvio Terzuoli;
2017-01-01

Abstract

Containment behaviour plays a key role in the safety framework of a Nuclear Power Plant. The GOTHIC thermal hydraulic code has been adopted to evaluate the Atucha-1 NPP containment responses during two postulated accident scenarios, Station Black Out and Large Break Loss of Coolant Accident, while assuming the external cooling of the Reactor Pressure Vessel is carried out during the transients. The Atucha-1 NPP has a containment designed to work at full pressure, constituted by a steel sphere enveloped by a concrete shell, and having an annular gap of air in between. The target of the analysis is the evaluation of the effects caused by the additional production of steam in the reactor cavity as a consequence of the ex-vessel cooling, which could cause an excessive pressurization of the containment, and lead to pressure values above the safety limit. The containment pressure and temperature, the distribution of hydrogen in the containment atmosphere and the water hold-up in the most relevant rooms have been monitored as target variables. Each accident scenario was simulated using two different nodalizations, characterized by a different level of refinement. The "detailed" nodalization is meant to be the most refined nodalization according to the available computational resources; having high fidelity three dimensional details, with a high number cells. While the "coarse" nodalization was developed in order to lower the demand for computational resources without significantly compromising the global scenario response. Both nodalizations are characterized by high complexity in the representation of rooms and their connections, e.g. all doors and blow off panels have been simulated to open with the designed differential pressure logic. Both accident transients, for each type of nodalization, were simulated for 200,000 seconds. Results showed that for the Large Break Loss of Coolant Accident pressure is predicted to reach around 5.25 bar, while the Station Black Out Scenario reaches 4.4 bar.
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11568/1050739
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