Published December 2010 | Version v1
Journal article

Current status of design and engineering analysis of Indian LLCB TBM

  • 1. Institute for Plasma Research, Bhat, Gandhinagar 382428, Gujarat (India)

Description

One of the key missions of the international thermonuclear experimental reactor (ITER) is to test and validate the various design concepts of tritium breeding blankets relevant to a power-producing reactor like DEMO. India has developed two breeding blanket concepts such as, lead lithium cooled ceramic breeder (LLCB) and helium cooled ceramic breeder (HCCB) for its DEMO. LLCB concept will be tested in ITER where Li2TiO3 ceramic breeder (CB) in the form of packed pebble beds is used as a tritium breeding material and PbLi eutectic is used as multiplier, breeder, and coolant for the CB zones. A detail engineering design and analysis has been executed for the LLCB TBM to optimize the flow parameters for helium and PbLi circuits, to estimate the temperature distribution in the various breeding zones and to ensure the thermal design limits for structural material and temperature window in ceramic breeder for effective tritium extraction. The detailed thermo-hydraulic CFD using Fluent and FE simulation studies will also be discussed in this paper.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2010.07.003

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2010.07.003;
PII
S0920-3796(10)00316-9;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
85
Journal Issue
10-12
Journal Page Range
p. 1966-1969
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
9. international symposium on fusion nuclear technology
Acronym
ISFNT-9
Dates
11-16 Oct 2009
Place
Dalian (China)

Optional Information

Copyright
Copyright (c) 2010 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.