Access the full text.
Sign up today, get DeepDyve free for 14 days.
Songlin Liu, Xuebin Ma, K. Jiang, Xiaoman Cheng, Kai Huang, H. Neilsion, A. Khodak, P. Titus (2017)
Conceptual design of the water cooled ceramic breeder blanket for CFETR based on pressurized water cooled reactor technologyFusion Engineering and Design, 124
I. Lengar, A. Čufar, S. Conroy, P. Batistoni, S. Popovichev, L. Snoj, B. Syme, R. Vila, G. Stankūnas (2016)
Radiation damage and nuclear heating studies in selected functional materials during the JET DT campaignFusion Engineering and Design, 109
Dong Lee, H. Jin, E. Lee, Suk-Kwon Kim, J. Yoon, K. Shin, Seungyon Cho (2016)
Thermal-Hydraulic Analysis for Conceptual Design of Korean HCCR TBM SetIEEE Transactions on Plasma Science, 44
(2018)
Design and thermal-hydraulic evaluation of helium-cooled ceramic breeder blanket for China fusion engineering test reactor
M. Shimada, A. Costley, G. Federici, K. Ioki, A. Kukushkin, V. Mukhovatov, A. Polevoi, M. Sugihara (2005)
Overview of goals and performance of ITER and strategy for plasma–wall interaction investigationJournal of Nuclear Materials, 337
G. Aiello, J. Aubert, L. Forest, J. Jaboulay, A. Puma, L. Boccaccini (2017)
Design of the helium cooled lithium lead breeding blanket in CEA: from TBM to DEMONuclear Fusion, 57
Yuntao Song, Song Wu, Jian Li, B. Wan, Y. Wan, P. Fu, M. Ye, Jinxing Zheng, K. Lu, Xiang Gao, S. Liu, Xu Liu, M. Lei, Xuebing Peng, Yong Chen (2014)
Concept Design of CFETR Tokamak MachineIEEE Transactions on Plasma Science, 42
N. Taylor, B. Merrill, L. Cadwallader, L. Pace, L. El-Guebaly, P. Humrickhouse, D. Panayotov, T. Pinna, M. Porfiri, S. Reyes, M. Shimada, S. Willms (2017)
Materials-related issues in the safety and licensing of nuclear fusion facilitiesNuclear Fusion, 57
Z. Xu, J. Rey, U. Fischer, A. Weth, C. Polixa (2006)
Development of a DEMO helium cooled pebble bed (HCPB) breeder unit featured in flat plates with meandering channels, 7181
M. Lei, Yuntao Song, M. Ye, K. Lu, K. Pei, Kun Xu, Shuling Xu (2015)
Conceptual Design of a Helium-Cooled Ceramic Breeder Blanket for CFETRFusion Science and Technology, 68
R. Zanino, L. Richard, F. Subba, S. Corpino, J. Izquierdo, R. Barbier, Y. Utin (2013)
CFD analysis of a regular sector of the ITER vacuum vessel. Part II: Thermal-hydraulic effects of the nuclear heat loadFusion Engineering and Design, 88
H. Bolt, V. Barabash, G. Federici, J. Linke, A. Loarte, J. Roth, K. Sato (2002)
Plasma facing and high heat flux materials-needs for ITER and beyondJournal of Nuclear Materials, 307
Y. Wan, Jian-gang Li, Yong Liu, Xiaolin Wang, V. Chan, C. Chen, X. Duan, P. Fu, Xiang Gao, K. Feng, Songlin Liu, Yuntao Song, P. Weng, B. Wan, F. Wan, Heyi Wang, Songtao Wu, M. Ye, Qingwei Yang, G. Zheng, Zhuang Ge, Qiang Li (2017)
Overview of the present progress and activities on the CFETRNuclear Fusion, 57
M. Lei, Yuntao Song, M. Ye (2015)
Thermal hydraulic analysis of the HECLIC blanket breeder unit for CFETRInternational Journal of Energy Research, 39
I. Fernández-Berceruelo, D. Rapisarda, I. Palermo, L. Maqueda, D. Alonso, T. Melichar, O. Frýbort, L. Vála, Á. Ibarra (2017)
Thermal-hydraulic design of a DCLL breeding blanket for the EU DEMOFusion Engineering and Design, 124
China Fusion Engineering Test Reactor, a fusion tokamak device, is proposed to provide complementary technology and experience for ITER and the future fusion power plant. A helium‐cooled ceramic breeder blanket concept is adopted as the candidate tritium breeding blanket for China Fusion Engineering Test Reactor. Detailed design of the blanket structure located at the outboard equatorial plane is presented. The coolant flow characters in the blanket were calculated by the theoretical method and the finite element method. The comparison of the calculated results was done, and it has a good agreement between theoretical results and simulation results. The results show that the pressure drop is 0.13 MPa and the total temperature rise is 194.6°C.
International Journal of Energy Research – Wiley
Published: Jan 25, 2018
Keywords: ; ; ; ;
Access the full text.
Sign up today, get DeepDyve free for 14 days.