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Latest News
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.”
H. Yoshida, the JT-60 Team
Fusion Science and Technology | Volume 26 | Number 3 | November 1994 | Pages 406-417
Magnetic Fusion Experiment | Proceedings of the Eleventh Topical Meeting on the Technology of Fusion Energy New Orleans, Louisiana June 19-23, 1994 | doi.org/10.13182/FST94-A40193
Articles are hosted by Taylor and Francis Online.
Recent results on JT-60U experimental activities are presented. High fusion performance of nD(0)τETi(0)=1.1×1021 m−3 s keV, QDT= 0.6, Sn= 5.1×1016 s−1, Ti(0)= 37 keV and H-factor = 3.6 has been achieved in the regime named “high-βp H-mode.” A fractional bootstrap current has reached ∼0.5 in a series of high fusion performance plasmas of Ip≤ 2.5 MA and Bt= 4.4 T. Attaining broadened pressure profile and peaked current profile, on the other hand, beta limit has substantially extended to βN= 4.2 and βp= 4.7 in a low current and field regime of Ip= 0.4∼0.9 MA and Bt= 1∼1.5 T. This operation regime has enabled quasi-steady state ELMy H-mode discharges to be sustained with the high performance of βN= 2.5∼3, βp= 2.5∼3.1 and H-factor = 1.8∼2.2 under non-inductive full current drive condition that the fraction of bootstrap current and beam driven current was 0.60 and 0.48, respectively, at Ip = 0.5 MA and Bt=1.5 T. LHCD has demonstrated the non-inductive current drive up to 3.6 MA and the current drive efficiency of 3.5×1019 m−2 A/W, while non-inductive full current drive has been also achieved by NB and NB+LHCD. Active current profile control has been successfully investigated by LH wave and tangential NB. In ELMy H-mode discharges there have been observed the reduction of the heat load on divertor plates and the reduction of the helium density in core plasma. Future plans of JT-60 program are presented, which include 500 keV negative-ion based NBI system, new radiative pumped divertor, and JT-60 Super Upgrade.