ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
Latest Magazine Issues
Jun 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
July 2026
Nuclear Technology
June 2026
Fusion Science and Technology
May 2026
Latest News
North American construction is back—smaller and faster—at OPG’s Darlington
“The nuclear renaissance is real here,” said Ontario Power Generation’s Subo Sinnathamby on May 8, one year to the day after OPG secured a final investment decision to build the first of four planned BWRX-300 reactors at its Darlington nuclear power plant, and shortly after the new reactor’s foundation was lifted into place. “We got our license to construct in April and our [final investment decision] in May, and we’ve been off to the races since.”
Nermin A. Uckan
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1444-1448
International Thermonuclear Experimental Reactor | doi.org/10.13182/FST92-A29924
Articles are hosted by Taylor and Francis Online.
The ranges of confinement-relevant (dimensional and dimensionless) plasma parameters for major tokamaks (JET, JT-60U, TFTR, DIII-D, …) that are expected to contribute to the ITER Physics R&D in the 1990s have been analyzed to characterize confinement and plasma performance in ITER-like designs. We find that the largest tokamaks (JET, JT-60U) should be able to demonstrate H-mode operation (with ELMs, as in ITER) with nτETi values within an order of magnitude of those required in ITER and have relevant dimensionless plasma parameters (ρ/a, ν*, etc.) within a factor 2 of those in ITER. Extrapolations from dimensionally similar discharges in DIII-D and JET show high-Q/ignition operation in ITER-like plasmas at plasma currents (∼16 MA) well below the nominal (22-MA) design value. Another critical issue for achieving ignition-level plasma performance is the anomalous alpha particle effects, mainly the “toroidal Alfvén eigenmode” (TAE mode). The D-T experiments in TFTR and JET (and simulations using fast beam ions) should realize alpha particle (fast-ion) parameters roughly similar, in relation to TAE mode thresholds, to those projected for ITER. We judge that present-day tokamaks will provide a sufficient database (by the mid-1990s) on H-mode confinement (with ELMs) and possible anomalous alpha particle effects at relevant dimensionless parameters that are expected to be adequate for ITER purposes.