Analysis of the Reflooding Process in Degraded Particle Beds by Simulations of the Debris Test Facility With the Severe Accident Analysis Code ASTEC V2.1 and COCOMO Code

Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation(2021)

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摘要
Abstract As part of a national research project RUB PSS investigates the cooling process of degraded core sections like debris beds and melt pools. Focus of these works is the simulation of the DEBRIS test facility located at IKE in Stuttgart with both the integral code ASTEC V2.1, developed by IRSN in France, and COCOMO, developed by IKE. In this work, the simulation of two bottom flooding experiments with similar temperature and pressure conditions but different particle types will be presented. The selected tests will be simulated with both a fixed input signal and a gravity-driven quench water flow similar to the actual test conditions. Focus of the analysis is on a comparison of the calculated and experimental results to validate the codes capabilities to simulate the most relevant phenomena which occur while quenching dry and overheated particle formations under varying thermohydraulic conditions. ASTEC is validated using numerous experiments like the PEARL tests that are comparable to those conducted within the DEBRIS test facility and disposes a well-developed model basis for the simulation of late phase phenomena. The resulting temperature evolutions are in good accordance with the experimental results. This is also reflected by the evolution of the quench front and also applies to the conducted COCOMO simulations. The released amount of steam is overestimated by both codes and leaves room for improvement.
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关键词
Beyond Design Basis Events,Thermal Hydraulics,Nuclear Safety and Security
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