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Comparative studies for two different orientations of pebble bed in an HCCB blanket

Plasma Science and Technology 2017年第12期19卷 146-153页

作者： Paritosh CHAUDHURI Chandan DANANI e rajendrakumar Institute for Plasma Research BhatGandhinagar-382 428India

The Indian Test Blanket Module（TBM） program in ITeR is one of the major steps in its fusion reactor program towards DeMO and the future fusion power reactor vision. Research and development（RD） is focused on two types of breeding blanket concepts： lead–lithium ceramic breeder（LLCB） and helium-cooled ceramic breeder（HCCB） blanket systems for the DeMO reactor. As part of the ITeR-TBM program, the LLCB concept will be tested in one-half of ITeR port no. 2, whose materials and technologies will be tested during ITeR operation. The HCCB concept is a variant of the solid breeder blanket, which is presently part of our domestic RD program for DeMO relevant technology development. In the HCCB concept Li_2TiO_3 and beryllium are used as the tritium breeder and neutron multiplier, respectively, in the form of a packed bed having edge-on configuration with reduced activation ferritic martensitic steel as the structural material. In this paper two design schemes, mainly two different orientations of pebble beds, are discussed. In the current concept（case-1）, the ceramic breeder beds are kept horizontal in the toroidal–radial direction. Due to gravity, the pebbles may settle down at the bottom and create a finite gap between the pebbles and the top cooling plate, which will affect the heat transfer between them. In the alternate design concept（case-2）, the pebble bed is vertically（poloidal–radial） orientated where the side plates act as cooling plates instead of top and bottom plates. These two design variants are analyzed analytically and 2 D thermal-hydraulic simulation studies are carried out with ANSYS, using the heat loads obtained from neutronic *** on the analysis the performance is compared and details of the thermal and radiative heat transfer studies are also discussed in this paper.

关键词： fusion reactor test blanket module HCCB thermal radiation heat transfer

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