Page 343 - Fundamentals of Magnetic Thermonuclear Reactor Design
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                Liquid breeding materials:
             l  Ensuring compatibility with structural materials.
             l  Breeding process research and development of relevant databases.
             l  Adjustment of optimised tritium extraction processes, and identification of
                relevant operating temperature ranges.
                Coolants:
             l  Ensuring compatibility with structural materials.
             l  Adjustment of processes for maintaining required coolant content and re-
                moving impurities, undesirable in terms of activation and corrosive effects.
             l  Development of heat-to-electricity conversion systems based on conven-
                tional energy processes.
                Protective barriers:

             l  Development of electrically insulating barriers to coat the walls of liquid-met-
                al ducts in blankets. These barriers should significantly reduce MHD pressure
                losses by decreasing electric currents generated by moving a metal through a
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                magnetic field. They must satisfy requirement ρδ > 0.02 Ωm , where ρ is the
                protective coating’s specific electrical resistance (Ω m), and δ is its thickness
                (m). Self-healing barriers are most attractive candidates. They result from a
                chemical interaction of a liquid metal’s individual components with a structur-
                al material’s ingredients. An alternative is a thin electrically conducting film
                separated from the duct by an electrically insulating layer.
             l  Development of anti-corrosion barriers at the duct wall–liquid metal inter-
                face, especially important for the Pb–Li coolant. In some cases, wall cor-
                rosion rate should be decreased by an order of magnitude and its tritium
                permeability, by 2–3 orders of magnitude.
             l  Development of tritium barriers on the liquid metal side or on the structure’s
                outboard side, as well as tritium barriers for the tritium circuit pipes.
             l  Experimental validation of the barriers’ operability at design temperatures,
                fast neutron fluence and expected durability.
                Radiation and environmental safety:
             l  Mitigation of operation risks and hazards associated with the chemical in-
                teraction of reactor materials (lithium or Pb–Li eutectic alloy with water
                and air, beryllium with water vapour, etc.) in off-normal situations to levels
                considered safe by socio-economic criteria.
             l  Prevention of tritium’s uncontrolled release from structural materials,
                beryllium, breeding materials and coolants in off-normal situations.
             l  Decrease in residual heat production and radioactive product release  in
                hypothetic off-normal situations to environmentally safe levels.
             l  Decrease in residual activation of materials to levels considered safe for
                their processing or shallow land burial.
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