A. Sabogal , C. Torregrosa-Martín , D. Rodríguez , C. Caballero , I. Podadera , A. Ibarra , D. Jimenez-Rey , F. Martin-Fuertes , A. Delgado , U. Ruiz de Gopegui , K. Garmendia
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引用次数: 0
Abstract
The IFMIF-DONES facility will irradiate prospective fusion reactor materials using a linear accelerator to collide a deuteron beam with a lithium target in a liquid state. A particularity of the IFMIF-DONES accelerator is the lack of physical separation between the target vacuum chamber (TVC), where liquid Li circulates, and the vacuum chambers of the upstream accelerator components. Loss of Vacuum Accidents (LOVAs) could thus result in the potential transport of material between the TVC and the rest of the accelerator, with the risk of potential reactions with the liquid Li or the mobilisation of radioactive inventory. This paper describes the Multipurpose Vacuum Accident Scenarios (MuVacAS) experimental setup, specifically designed to validate mitigation strategies against of such accidents. MuVacAS replicates the key characteristics of the last 49 m of the IFMIF-DONES accelerator vacuum chambers. It is equipped with modules to reproduce different leak scenarios, including sudden air inrushes or the controlled injection of various gases and water. Initial experimental results from a sudden air inrush scenario are presented, showcasing the capability of MuVacAS to accurately reproduce accident conditions in vacuum systems. Furthermore, the measurement systems were reliable during the tests, ensuring the data were valid and accurate. The planned experimental campaigns aimed at reproducing a variety of LOVAs are also outlined. The data collected in these campaigns will be used to assess the effectiveness of the Fast Safety Isolation Valves (FSIVs) — the primary mitigation devices for these accidents — and to support the design of the IFMIF-DONES safety systems.
期刊介绍:
The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.