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Abstract: According to the Technical program of cooperation between the leading research institutes of India and Russian Federation the joint development of lead-lithium ceramic breeder (LLCB) test blanket module (TBM) is one of preferential directions in this program. The concept of LLCB TBM and corresponding DEMO blanket has been proposed by Indian TBM Team and India is a “Leader” in this concept. Russian Federation takes part in the design, analysis and R&D activities on LLCB TBM concept on the rights of “Partner”. In particular the joint efforts are focused now on the development of LLCB TBM in the electromagnetic option (so-called EM-TBM). In the framework of the design and analysis for LLCB TBM several design options have been considered by RF specialists during 2010–2011 period. The main directions of design and analysis works are as follows: [-] the designing of TBM load-bearing casing including the reliable cooling layout; [-] the development of tritium breeding zone (TBZ) basing upon the minimizing of MHD-pressure drops for liquid metal circulation, increasing of eutectic outlet temperature (up to 500°C) and tritium production rate; [-] to create the TBM attachment system that will be able to withstand the loads for all the ITER operation modes; [-] thermal hydraulic analyses for TBM helium cooling system and eutectic circuit (taking into account the magnetic field conditions); Brief results of this activity and consequent proposals on the design improvements are presented in this paper. The critical issues and further plans on the development of LLCB TBM in Russian Federation are also discussed and analyzed in this article. [Copyright &y& Elsevier]

Abstract: Several types of reduced activation ferritic/martensitic (RAFM) steel have been developed over the past 30years in China, Europe, India, Japan, Russia and the USA for application in ITER test blanket modules (TBMs) and future fusion DEMO and power reactors. The progress has been particularly important during the past few years with evaluation of mechanical properties of these steels before and after irradiation and in contact with different cooling media. This paper presents recent RAFM steel results obtained in ITER partner countries in relation to different TBM and DEMO options. [Copyright &y& Elsevier]