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Fusion Science and Technology
Delay, cost increase announced for U.K. nuclear project
Perspex screens and reduced seating capacity in the Hinkley Point canteens help protect the workforce during breaks, EDF Energy said. Photo: EDF Energy
The unfortunate effects of the COVID-19 pandemic on nuclear new-build projects haven’t stopped with Vogtle: EDF Energy this morning reported that the expected startup date for Unit 1 at its Hinkley Point C site is being pushed from late 2025 to June 2026.
In addition, the project’s completion costs are now estimated to be in the range of £22 billion to £23 billion (about $30.2 billion to $31.5 billion), some £500 million (about $686 million) more than the 2019 estimate, EDF said, adding the caveat that these revisions assume an ability to begin a return to normal site conditions by the second quarter of 2021.
J. A. Leuer, B. J. Xiao, D. A. Humphreys, M. L. Walker, A. W. Hyatt, G. L. Jackson, D. Mueller, B. G. Penaflor, D. A. Piglowski, R. D. Johnson, A. S. Welander, Q. P. Yuan, H. Z. Wang, J. R. Luo, EAST Team
Fusion Science and Technology | Volume 57 | Number 1 | January 2010 | Pages 48-65
Technical Paper | dx.doi.org/10.13182/FST10-A9268
Articles are hosted by Taylor and Francis Online.
The Experimental Advanced Superconducting Tokamak (EAST) was the first shaped tokamak of mega-ampere scale to achieve plasma utilizing a fully superconducting poloidal field coil system, and it is addressing ITER relevant superconducting constraints associated with the breakdown, plasma formation, and initial plasma current ramp. Electric field production for plasma start-up is severely limited in fully superconducting machines as a consequence of constraints associated with coil and lead voltages and eddy current heating in the superconducting coils. Such constraints motivate the use of electromagnetic modeling codes to design start-up scenarios for these devices. The successful first plasma campaign of the EAST superconducting tokamak was greatly facilitated by extensive and careful planning, development of appropriate modeling, simulation and diagnostic tools, a highly flexible plasma control system, and a highly experienced international collaboration team. We describe the design and modeling tools used to develop the first plasma scenario along with results of their application in the start-up campaign. Control design tools and plasma control algorithms utilized during the first campaign are discussed. Key physics, engineering, and operations results of the first plasma campaign are presented, including observations relevant to future devices such as ITER.