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Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
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.
