Flow Distribution Analysis of Water-Cooled Solid Breeder Test Blanket Module
Tóm tắt
Từ khóa
Tài liệu tham khảo
J.G. Li, Missions & Integration Design of CFETR (2012), Workshops on MFE Development Strategy in China. http://cnmfrdg.ustc.edu.cn/workshop/Second/201205/P020120605453815665292.pdf
Y. Someya, K. Tobita, H. Utoh, A feasible DEMO blanket concept based on water cooled solid breeder. in 24th IAEA Fusion Energy Conference
C. Amador, A. Gavriilidis, P. Angeli, Flow distribution in different microreactor scale-out geometries and the effect of manufacturing tolerances and channel blockage. Chem. Eng. J. 101(1–3), 379–390 (2004)
H. Liu, P. Li, J.V. Lew, CFD study on flow distribution uniformity in fuel distributors having multiple structural bifurcations of flow channels. Int. J. Hydrogen Energy 35(17), 9186–9198 (2010)
A. Ying, M. Narula, R. Hunt et al., Integrated thermo-fluid analysis towards helium flow path design for an ITER solid breeder blanket module. Fusion Eng. Des. 82(15), 2217–2225 (2007)
P. Chaudhuri, C. Danani, V. Chaudhari et al., Thermal–hydraulic and thermo-structural analysis of first wall for Indian DEMO blanket module. Fusion Eng. Des. 84(2), 573–577 (2009)
M. Akiba, M. Enoeda, D. Tsuru et al., Development of water-cooled solid breeder test blanket module in JAEA. Fusion Eng. Des. 84(2), 329–332 (2009)
K. Ezato, Y. Seki, H. Tanigawa et al., Thermo-hydraulic testing and integrity of ITER test blanket module (TBM) first wall mock-up in JAEA. Fusion Eng. Des. 85(7), 1255–1260 (2010)
Y. Seki, Y. Ohnishi, A. Yoshikawa et al., Numerical simulation of turbulent flow of coolant in a test blanket module of nuclear fusion reactor. Prog. Nucl. Sci. Technol. 2, 139–142 (2011)
Tokamak Cooling Water System, DDD2_22LB64_v1_0. 15 June 1998
Z. Zhao, K. Feng, G. Zhang et al., Transient thermal analysis for the first-wall of CH HCSB TBM. Nucl. Fusion Plasma Phys. 4, 012 (2009)