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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.”
Marco Ferrari, Massimo Furrer, Giorgio Simbolotti, Carlo Talarico
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 1011-1015
Fusion Blanket and Shield Technology | doi.org/10.13182/FST96-A11963069
Articles are hosted by Taylor and Francis Online.
Following a preliminary test campaign (200 thermal cycles) on a solid breeder blanket mockup, an extended test campaign (about 1000 thermal cycles) has been carried out by ENEA. The duration of the test campaign represents a significant fraction of the blanket module lifetime in the ITER device. In particular, these out-of-pile experiments have been performed in order to test (both functional and endurance testing) the thermal-hydraulic and thermo-mechanical performance of a water cooled breeder-in-tube blanket mockup (1-PIN) using Li2ZrO3 pebbles as a breeder material.
The test campaign has been completed and the resulting data concerning thermal and thermal-hydraulic parameters have been elaborated and analyzed by means of a comparison with theoretical predictions based on a proper thermal-hydraulic model.
The post test examination of the pebbles is in progress in order to investigate the thermo-mechanical behavior of the breeder material under cycling.
The paper deals with the first part of the results.