Abstract

Korea has developed a Helium Cooled Ceramic Reflector (HCCR) Test Blanket Module (TBM) for testing in ITER and it consists of the functional components to distribute the He coolant to each region such as First Wall (FW), Breeding Zone (BZ), Side Wall (SW), and Back Manifold (BM). In the current study, the detailed design of each components were introduced as follows; (1) FW considering cooling under structural material temperature limit (550 °C); (2) BZ layer for obtaining tritium breeding ratio and cooling with breeder, reflector, and multiplier pebbles; (3) SW considering the flow distribution to BZ and internal pressure; (4) BM for uniform flow to FW cooling channels; and (5) He purge line in BZ considering purge gas distribution in BZ. From the analysis with the CFD code, ANSYS-CFX with the results of nuclear heating by neutronic analysis, the performances of each functional components were investigated and it is confirmed that their performances were satisfied the design requirements of KO HCCR TBM.

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