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Second round of Launch Pad selections includes eight newcomers
The National Reactor Innovation Center at Idaho National Laboratory has announced 13 project selections across 12 companies for the Nuclear Energy Launch Pad, a Department of Energy–led program that integrates reactor and fuel facility authorization, testing, and deployment support for private nuclear developers.
The Launch Pad emerged from the Reactor Pilot Program and Fuel Line Pilot Program.
According to INL, projects selected include reactor development and nuclear fuel cycle advancements, including fabrication, enrichment, and conversion technologies.
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.