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Abstract: The nature convection of the liquid LiPb, due to thermal diffusion, in the poloidal channel perpendicular to the strong magnetic field in the blanket has been considered and studied. The cubic enclosure filled by the liquid metal LiPb flow is assumed as the analyzed model. It was numerical simulated by three-dimensional CFD with special MHD code. The Hartmann number is from 20 to 200. The wall of the enclosure was heated by a uniform temperature and the other wall was cooled along two opposite vertical walls, all other walls being adiabatic. The momentum equation and electrical-magnetic equations for the liquid LiPb flow in the enclosure have given. It is assumed the nature convection be steady-state conditions. The velocity and temperature of the LiPb flow with differential Hartmann number is discussed. The temperature distribution is changed due to magnetic field. The heat convection is enhanced by the high Hartmann number which the magnetic field intensified the motion of the LiPb fluid in the side layer. There is a strong thermal coupling, modifying importantly the magnitude of the flow. [ABSTRACT FROM AUTHOR]

Numerical simulation of magnetohydrodynamic (MHD) flow is implemented by using the commercial code package PHOENICS, in which the momentum source term of Lorentz force is added by applying FORTAN subroutine. Assuming simplified condition of a square duct, the numerical approach is applied to simulate the velocity profile in MA-zone in the design of dual-cooled waste transmutation blanket (DWTB) for a fusion-driven sub-critical system (FDS). The high velocity of closing FW side will improve the heat transfer between liquid metal and the walls of duct, due to high Hartmann number, but the MHD pressure drop will be increased. The compromise between the heat transfer and MHD pressure drop can be taken as reference for the design of the transmutation blanket. [Copyright &y& Elsevier]

A conceptual structure design and the thermal-hydraulic analysis of the pressurized helium gas and LiPb eutectic dual-cooled waste transmutation blanket for the Fusion-Driven Sub-critical System (FDS), which is being designed for multi-purposes (transmuting nuclear wastes from fission power plants, breeding fissionable nuclear fuel for fission power plants and breeding tritium for sustainable operation) based on the Tokamak fusion core with the minor radius of 1 m, the major radius of 4 m, the elongation of 1.7 and the responding neutron wall loading of 0.5 MW/m2, have been presented. [Copyright &y& Elsevier]

Abstract: EAST is a non-circular advanced steady-state experimental device and the first entirely superconducting tokamak in the world. Vacuum system is one of the most important sub-systems of EAST device. Wall conditionings, such as baking, discharge cleaning and boronization, also play a very important role for the plasma operation. Due to Ion Cyclotron Resonance Frequency (ICRF) wall conditioning technique could be carried out in the presence of a high toroidal magnetic field, it is routinely used for wall cleanings on EAST. After the 2nd campaign in 2007, the plasma facing walls was modified to full carbon walls and vacuum system was upgraded to meet the requirement of particles exhaust. This paper will introduce the new statues of vacuum system, such as pumping, fueling and wall conditionings on EAST. Then the vacuum operation and wall conditioning in the 2008 campaign is introduced. [Copyright &y& Elsevier]

Abstract: Testing of breeding blanket module (TBM) is one of ITER''s important objectives. China is performing design and technology development of ITER TBMs based on the development strategy of fusion DEMO in China. Solid breeder with helium-cooled test blanket module concept for test in ITER should be the basic option in China. The progress and status of China helium-cooled solid breeder (CH HCSB) TBM since 2004 are introduced briefly. Concept designs of HCSB TBM and ancillary systems, test strategy for their tests in ITER, key R&D issues are summarized in this paper. An international collaboration in R&D, development and testing of TBMs are proposed. [Copyright &y& Elsevier]

Abstract: Preliminary design and analysis for China helium-cooled solid breeder (CH HC-SB) test blanket module (TBM) for testing in ITER device have been carried out recently. In this paper, the design description, the performance analysis and the related ancillary systems for CH TBM are given. The key features of the design are based upon the breeder-outside-tube (BOT) concept, on the use of solid breeder ceramic material, of helium as coolant and tritium purge gas, of ferrite–martensite steel as structural material and of beryllium as neutron multiplier. Results show that the proposed TBM concept has the advantages of higher tritium breeding ratio (TBR), simple structure design and engineering feasibility. [Copyright &y& Elsevier]