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North American construction is back—smaller and faster—at OPG’s Darlington
“The nuclear renaissance is real here,” said Ontario Power Generation’s Subo Sinnathamby on May 8, one year to the day after OPG secured a final investment decision to build the first of four planned BWRX-300 reactors at its Darlington nuclear power plant, and shortly after the new reactor’s foundation was lifted into place. “We got our license to construct in April and our [final investment decision] in May, and we’ve been off to the races since.”
J. Q. Ling W. D. Booth, R. Carrera, D. Tesar
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1823-1827
Impurity Control and Plasma-Facing Component | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29609
Articles are hosted by Taylor and Francis Online.
A remote system is considered for the in-vessel maintenance of the IGNITEX device. The specified maintenance tasks include: inspection, coating repair of the first wall, and cleaning of the vacuum vessel. In this paper the conceptual design of the in-vessel remote maintenance system (IVRMS) is presented. The IVRMS consists of a manipulator chain, a series of dedicated tools as end-effectors, a control system, and a delivery system. A manipulator of snake type with 11 degrees of freedom (DOF), consisting of a toroidal chain (6 links) and a poloidal chain (3 links), is used to provide 90° toroidal reach and 360° poloidal reach in the IGNITEX vacuum vessel. The mechanical structure design of the manipulator uses light weight and compact actuator modules and carbon fiber materials for the links. The interface of the IVRMS with the IGNITEX system is described. A system control layout including the hardware and software architecture is discussed. The concept and implementation of this design provides general features for in-vessel remote maintenance of a small fusion tokamak.