Title :
Progress of Functional Components Design and Analysis of a Korean HCCR TBM in ITER
Author :
Dong-Won Lee ; Hyung Gon Jin ; Kyu In Shin ; Eo Hwak Lee ; Suk-Kwon Kim ; Jae Sung Yoon ; Mu-Young Ahn ; Seungyon Cho
Author_Institution :
Korea Atomic Energy Res. Inst., Daejeon, South Korea
Abstract :
Korea has developed a helium cooled ceramic reflector (HCCR) test blanket module (TBM) for testing in a ITER, which consists of functional components to distribute the He coolant to each region such as the first wall (FW), breeding zone (BZ), side wall (SW), and back manifold (BM). In this paper, the detailed design of each component is introduced as follows: 1) FW considering cooling under a structural material temperature limit (550 °C); 2) BZ layer for obtaining tritium breeding ratio and cooling with a 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 a purge gas distribution in BZ. From the performance analysis of each functional component using the CFD code, ANSYS-CFX with the results of nuclear heating from a neutronic analysis, the results show that the design requirements of KO HCCR TBM were satisfied.
Keywords :
ceramics; computational fluid dynamics; fusion reactor blankets; fusion reactor design; ANSYS-CFX; CFD code; FW cooling channels; He coolant; He purge line; ITER; Korean HCCR TBM analysis; back manifold; breeder; breeding zone; first wall; functional components design; helium cooled ceramic reflector; multiplier pebbles; neutronic analysis; nuclear heating; side wall; structural material temperature limit; temperature 550 C; test blanket module; tritium breeding ratio; Coolants; Heating; Helium; Plasma temperature; Temperature distribution; Breeding zone (BZ); He cooling; ITER; first wall (FW); flow distribution; test blanket module (TBM); test blanket module (TBM).;
Journal_Title :
Plasma Science, IEEE Transactions on
DOI :
10.1109/TPS.2014.2309913