Remote handling (RH) procedures in fusion devices are sufficiently complex that a purely virtual verification and validation (V&V) process cannot guarantee reliable operation. Dedicated physical testing in purpose-built facilities is essential to validate and commission RH equipment and to train operators. As part of the divertor Tokamak test (DTT) project, the REMote HAndling Test and training facility (REMHAT) is currently under procurement. Its requirements and functions have been defined, and a preliminary logical architecture has been established. The facility comprises four main subsystems—buildings&services, mock-ups, robots, and control system. Given the integration of multiple subsystems and stakeholders, interface management has been a central focus throughout the procurement packages. Building on a previously presented conceptual design, this article reports advances in the final design of REMHAT and the management of interfaces across subsystems. The mock-ups reproduce the geometry, mass, and stiffness of the relevant DTT components, enabling representative testing of RH equipment and procedures. A model-based approach using the systems modeling language (SysML) has been adopted to manage requirements, functions, and interfaces—particularly between the robots and the control system—resulting in a consistent logical architecture and more efficient conflict resolution among requirements. The final design for the robots and the control system, together with manufacturing activities, is expected to be completed by 2026.

Interface Management in the Development of the DTT Remote Handling Facility—REMHAT / Marino, F., Fimiani, A., Zoppoli, A., Reale, A., Dalla Palma, M., Carrelli, C., Di Gironimo, G.. - In: IEEE TRANSACTIONS ON PLASMA SCIENCE. - ISSN 0093-3813. - (2026), pp. 1-8. [10.1109/TPS.2026.3665124]

Interface Management in the Development of the DTT Remote Handling Facility—REMHAT

Francesco Marino;Andrea Fimiani;Andrea Zoppoli;Giuseppe Di Gironimo
2026

Abstract

Remote handling (RH) procedures in fusion devices are sufficiently complex that a purely virtual verification and validation (V&V) process cannot guarantee reliable operation. Dedicated physical testing in purpose-built facilities is essential to validate and commission RH equipment and to train operators. As part of the divertor Tokamak test (DTT) project, the REMote HAndling Test and training facility (REMHAT) is currently under procurement. Its requirements and functions have been defined, and a preliminary logical architecture has been established. The facility comprises four main subsystems—buildings&services, mock-ups, robots, and control system. Given the integration of multiple subsystems and stakeholders, interface management has been a central focus throughout the procurement packages. Building on a previously presented conceptual design, this article reports advances in the final design of REMHAT and the management of interfaces across subsystems. The mock-ups reproduce the geometry, mass, and stiffness of the relevant DTT components, enabling representative testing of RH equipment and procedures. A model-based approach using the systems modeling language (SysML) has been adopted to manage requirements, functions, and interfaces—particularly between the robots and the control system—resulting in a consistent logical architecture and more efficient conflict resolution among requirements. The final design for the robots and the control system, together with manufacturing activities, is expected to be completed by 2026.
2026
Interface Management in the Development of the DTT Remote Handling Facility—REMHAT / Marino, F., Fimiani, A., Zoppoli, A., Reale, A., Dalla Palma, M., Carrelli, C., Di Gironimo, G.. - In: IEEE TRANSACTIONS ON PLASMA SCIENCE. - ISSN 0093-3813. - (2026), pp. 1-8. [10.1109/TPS.2026.3665124]
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11588/1050694
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