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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.”
E. S. Hotston
Fusion Science and Technology | Volume 26 | Number 3 | November 1994 | Pages 203-221
Technical Paper | Divertor System | doi.org/10.13182/FST94-A30323
Articles are hosted by Taylor and Francis Online.
The exhaust modeling program for a fusion reactor based on a tokamak carried out for Next European Torus (NET)/International Tokamak Reactor (INTOR)/International Thermonuclear Experimental Reactor (ITER) in the years 1982 to 1991 during which the author was involved is open to criticism on at least two counts. The first is that although in general there are at least two plasma configurations in the divertor that balance the upstream plasma pressure and power flow into the divertor, only one solution was accepted. The other solutions were assumed to be nonexistent or unimportant. The second count is that the possibility was not considered that atoms backscattered from the plasma could deposit power in the divertor target; inclusion of this process would have enlarged the domain in which multiple solutions are important. In particular, a plasma in which the temperatures are low appears as a possible solution. Here the atomic and molecular properties of the fuel, which vary quite rapidly with the electron temperature, are very important, so obtaining this solution by an implicit procedure is difficult. The two-dimensional modeling programs referred to earlier were carried out with the use of the Braams plasma transport code, which relies on a “strongly implicit method” for its updating. Examination of this code shows that the techniques used to stabilize it are incompatible with the procedures required to find the low-temperature solution. These objections would remain in the case where a Monte Carlo code is used to trace the fate of the neutrals recycled in the divertor. Recent modeling work based on Monte Carlo codes suggests that the plasma temperatures of the higher temperature solutions are likely to be greater than previously thought. Thus, resolution of the problem of finding the lower temperature solutions becomes important.