Investigation of heat transfer in a steam generator bayonet tube for the development of PbLi technology for EU DEMO fusion reactor

被引:15
作者
Martelli, E. [1 ]
Del Nevo, A. [2 ]
Lorusso, P. [3 ]
Giannetti, F. [3 ]
Narcisi, V [3 ]
Tarantino, M. [2 ]
机构
[1] ENEA, Dept Fus & Nucl Safety Technol, I-00044 Rome, Italy
[2] ENEA, Dept Fus & Nucl Safety Technol, I-40032 Camugnano, BO, Italy
[3] Sapienza Univ Rome, DIAEE Dept, I-00186 Rome, Italy
关键词
DEMO; RELAP5; Heat transfer; PbLi loop; WCLL BREEDING BLANKET;
D O I
10.1016/j.fusengdes.2020.111772
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
In the frame of the EUROfusion roadmap for the development of the DEMO power plant, a research activity was carried out to develop a Lithium-Lead/water heat exchanger. The component should be capable to remove nuclear heat deposited in the liquid metal of the Dual Coolant Lithium Lead breeding blanket and feeding a steam turbine, ensuring an efficient thermal power conversion to electricity. One of the selected configurations is the steam generator bayonet tube. The HERO test section is an experimental mock-up in a relevant scale of this steam generator, consisting of a bundle of seven double-wall bayonet tubes with a leakage monitoring system. This test section, developed by ENEA at Brasimone Research Center and installed in the main vessel of the CIRCE pool facility, aims to investigate the thermal-hydraulic features of the system, providing a database for thermal-hydraulic system codes validation. An experimental campaign was carried out to demonstrate technological feasibility and performances of the prototypical heat exchanger, suitable as steam generator for the PbLi loop of the Dual Coolant Lithium Lead and Water Cooled Lithium Lead breeding blankets. A post-test analysis has been realized with RELAP5-3D and RELAP5/Mod3.3 codes in order to evaluate code capability in simulating heat transfer in liquid metal side.
引用
收藏
页数:6
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