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

P2.170 Helium Cooling Systems for Indian LLCB TBM

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: 170
Poster H. Fuel Cycle and Breeding Blankets P2 Poster session

Speaker

Brijesh Kumar Yadav (Institute for Plasma Research)

Description

Indian Lead Lithium cooled Ceramic Breeder (LLCB) Test Blanket Module (TBM) will be tested in one half of the port no#02 of ITER. In LLCB TBM, PbLi eutectic alloy is used as multiplier, breeder, and coolant for the CB zones, and Li2TiO3 ceramic breeder (CB) is used as a tritium breeding material. The LLCB TBM consists of two helium coolant circuits, one for the TBM outer box i.e. the TBM First Wall (FW) and the top, bottom and back plates and other for the Pb-Li eutectic, which cools the Ceramic Breeder (CB) packed beds. The outer box structure is India specific Reduced Activation Ferritic Martensitic Steel (IN-RAFMS) and is cooled by high pressure-high temperature (8 MPa - 300 C) helium gas named as FWHCS. The FWHCS is to extract the incident surface heat flux from plasma and, partially, the neutronic heat deposited in the RAFMS box structure and Pb-Li interface locations. The molten Pb-Li eutectic, flows separately around the lithium ceramic breeder pebble bed compartments to extract heat from the CBs. The Pb-Li flow velocity is kept moderate enough such that its self-generated heat and the heat transferred from the ceramic breeder bed is extracted effectively. The second helium circuit extracts heat from the molten Pb-Li eutectic and is named as LLHCS. Eventually, the helium systems transfer the heat to Component Cooling Water System (CCWS) of ITER.  The requisite from the two helium systems are that they shall provide the coolant at the characteristic pressure, temperature and mass flow rate required by the TBM for testing and extraction of the heat produced. This paper discusses about design parameters of the two helium cooling systems, operational states of the systems w.r.t the ITER machine operation, system`s behavior during ITER Operation, and assembly of the coolant systems in TCWS Vault annex.

Co-author

Brijesh Kumar Yadav (Institute for Plasma Research, Gandhinagar, India)

Presentation Materials

There are no materials yet.