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- W1514348085 abstract "It has been proposed that testing fusion first wall/blanket/shield (FW/B/S) components in a fission reactor could provide timely solutions to some engineering problems that should be solved before the next generation of fusion reactors such as FED and INTOR can be built and operated reliably. It was earlier demonstrated that bulk heating rates in fusion FW/B/S could be simulated in the Engineering Test Reactor (ETR) at the Idaho National Engineering Laboratory thus making integral thermal-hydraulic and cooling systems testing feasible in certain existing fission reactors. This paper extends these results by describing the calculations in some detail and comparing the neutronics of the tokamak FW/B/S with the same system in the ETR." @default.
- W1514348085 created "2016-06-24" @default.
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- W1514348085 date "1980-12-01" @default.
- W1514348085 modified "2023-09-28" @default.
- W1514348085 title "Heating calculations of fusion blanket experiments in a fission reactor" @default.
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