5-9 September 2016
Prague Congress Centre
Europe/Prague timezone

P2.193 A comparative study on two DEMO-relevant test blanket modules

6 Sep 2016, 14:20
1h 40m
Foyer 2A (2nd floor), 3A (3rd floor) (Prague Congress Centre)

Foyer 2A (2nd floor), 3A (3rd floor)

Prague Congress Centre

5. května 65, Prague, Czech Republic
Board: 193
Poster J. Power Plants Safety and Environment, Socio-Economics and Technology Transfer P2 Poster session

Speaker

Dagui Wang (Institute of Nuclear Energy Safety)

Description

Breeding blanket research and development is recognized as one of the most important areas for realizing an energy-producing fusion reactor. In China, the ceramic breeder/helium coolant/ferritic steel structure is considered as the main concepts of the blanket to conduct the breeding blanket research, and on the other hand, the liquid breeder blanket is also to be investigated as the alternative option. Helium cooled ceramic breeder (HCCB) TBM is one of China’s TBM concepts. HCCB TBM uses Li4SiO4 pebble as tritium breeder and Beryllium pebbles as neutron multiplier. The structure material is reduced activation ferritic/martensitic steel. High pressure (8 MPa) helium will flow through the cooling channels inside structures to carry out heat. The generated tritium will be extracted by low pressure (about 1 atm) helium purge gas flow through pebbles. The dual functional lithium-lead test blanket module (DFLL TBM) is another concept of TBM concepts. DFLL TBM design has the flexibility of testing both the helium-cooled quasi-static lithium-lead (SLL) blanket concept and the He/PbLi dual-cooled lithium-lead (DFLL) blanket concept. In this paper, the RAMI approach is used to compare those two TBM conceptual designs. The two conceptual designs have been compared from the function, risk level, system reliability and operation availability. In the compare progress, the function breakdown was performed on those two conceptual designs. Based on the result of function breakdown, the reliability model were established for those two TBMs and the inherent availability are  94.69% for HCCB TBS and 98.57% for DFLL TBS over two years based on the ITER reliability database. Besides, the Failure Modes Effects and Criticality Analysis (FMECA) is also performed on those two TBMs with criticality charts highlighting the risk level of the different failure modes with regard to their probability of occurrence and their effects on the availability.

Co-author

Dagui Wang (Institute of Nuclear Energy Safety, HeFei, China)

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