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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.