Speaker
Qunying Huang
(Key Laboratory of Neutronics and Radiation Safety)
Description
The dual functional lead lithium (DFLL) test blanket module (TBM) concept has been proposed by FDS team to demonstrate the techniques basis of DEMO liquid blanket concepts, including quasi-statistic lead lithium (SLL) breeder blanket and the dual-cooling lead lithium (DLL) blanket.
In recent years, series R&D work for DFLL-TBM carried out are mainly on five topics: 1) Structural materials (i.e. CLAM steel) qualification; 2) PbLi/He coolant technologies and safety issues; 3) RAMI (Reliability, Availability, Maintainability and Inspectability) estimation of DFLL blanket; 4) Small TBM mockup neutronics experiments; 5) Tritium behavior in CLAM steel.
The latest progress is as follows:
The fabrication technologies were mature and the properties basically met with the requirement of TBM.
The double-coolant multi-function experimental loop DRAGON-V is being built and the construction will be finished at the end of 2016 and then the out of pile tests can be performed with it. On the other hand, the construction of the high intensity neutron generator (HINEG) for D-T fusion neutrons has been finished and the experiments related to the D-T fusion neutrons and materials are being carried.
The RAMI analysis was performed on the conceptual design of DFLL-TBM. The inherent availability of the DFLL-TBM system after implementation of mitigation actions for total 181 failure modes was calculated to be 98.57% for 2 years’ operation.
A small blanket mock-up has been fabricated and the preliminarily D-T neutrons irradiation results validated the precision of the data library and the reasonableness of the TBM design.
Permeation experiments of hydrogen and deuterium has been performed, the transport parameters and results were obtained and consistent well with the results of other RAFM steels.
Based on the latest R&D progress, the status and strategy of DFLL blanket for DEMO are presented in the paper.
Keywords: Fusion Reactor; Liquid Breeder Blanket; DFLL-TBM; Development Roadmap
Co-author
Qunying Huang
(Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, China)
