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Vogtle-3 shuts down for valve issue
One of the new Vogtle units in Georgia was shut down unexpectedly on Monday last week for a valve issue that has since been investigated and repaired. According to multiple local news outlets, Georgia Power reported on July 17 that Unit 3 was back in service.
Southern Company spokesperson Jacob Hawkins confirmed that Vogtle-3 went off line at 9:25 p.m. local time on July 8 “due to lowering water levels in the steam generators caused by a valve issue on one of the three main feedwater pumps.”
P. H. Rebut, B. E. Keen
Fusion Science and Technology | Volume 11 | Number 1 | January 1987 | Pages 13-42
Overview | JET Project | doi.org/10.13182/FST87-A24999
Articles are hosted by Taylor and Francis Online.
The background to the decision to build the Joint European Torus (JET) is described, and a brief introduction to the main aims, overall design philosophy, and the planned parameter range of the large tokamak device (major radius R = 2.96 m; horizontal and vertical minor radii a = 1.25 m and b = 2.10 m, respectively; plasma current Ip = 4.8 MA) is provided. JET is situated on the Culham Laboratory site, United Kingdom, and its main objective is to obtain and study plasmas in conditions and with dimensions approaching those needed in a fusion reactor. The main emphasis in the initial operation has been in the ohmic heating phase, in which results have covered a wide range of parameters: plasma currents Ip < 5 MA; toroidal magnetic fields BT = 1.3 to 3.4 T; elongation ratios b/a = 1.2 to 1.7; and safety factor values q = 2.2 to 12. Average electron densities ne = (1 to 4) × 1019 m-3, with high central electron temperatures (Te up to 5 keV) and ion temperatures (Ti up to 4 keV) have been achieved, although Zeff was in the range of 2.5 to 10. Energy confinement times (τE) of up to 0.8 s have been obtained. Some problems with metallic and low-Z impurities are noted, causing high radiation levels. Initial experiments, with ion cyclotron resonance frequency (ICRF) heating of hydrogen and 3He minorities in deuterium plasmas at megawatt levels, are reported. A discussion of certain limitations observed generally in tokamaks and how these might affect future developments of the JET program is presented. Planned future experiments on impurity control, additional heating (ICRF ≈ 15 MW, and neutral injection ≈ 10 MW), and preparations for tritium operation are also described.