Page 344 - Fundamentals of Magnetic Thermonuclear Reactor Design
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320     Fundamentals of Magnetic Thermonuclear Reactor Design


               Development and experimental verification of computational codes:
            l  Neutron  science  computations  needed  to  determine  the  TBR,  radiation
               energy release, shielding properties and drop in residual energy release/
               radioactivity.
            l  Thermal physics and hydraulics computations with respect to intense heat
               fluxes and volume energy release, with due account for convective and
               radiative forms of heat transfer.
            l  MHD calculations for an electrically conductive liquid moving in complex-
               geometry ducts through a 3D magnetic field.
            l  Electromagnetic computations for an abruptly changing magnetic field.
            l  Mechanical strength analysis in a complex-geometry structure with account
               for the meaningful time evolution of materials’ properties.
               Development and pilot production of new measuring and diagnostic instru-
            ments able to retain their function in fusion reactor severe environment. The
            values to be controlled are the following:

                                             −2
                                        19
            l  neutron flux density (up to ∼10  cm ),
            l  tritium breeding rate,
            l  magnetic field strength (up to ∼16 T),
            l  temperature (20–1000)°C,
            l  gas, water and liquid metal pressures,
            l  coolant flow rate,
            l  tritium flows,
            l  coolant impurity content,
            l  mechanical stresses, deformations and dislocations in the structure,
            l  electromagnetic forces.

            REFERENCES

              [1]  V.N. Mikhailov,  V.A. Evtikhin, I.E.. Lyublinskij, et  al.
                                         (Lithium in Fusion Power and Space Engineering),
                Energoatomizdat, Moscow,  (1999) pp. 1–528 (in Russian).
              [2]  B.N. Kolbasov, V.A. Belyakov, E.N. Bondarchuk, et al. Russian concept for DEMO-S demon-
                stration power reactor, Fusion Eng. Des. 83 (2008) 870–876.
              [3]  A. Ying, M. Abdou, C. Wong, et al. An overview of US ITER test blanket module program,
                Fusion Eng. Des. 81 (2006) 433–441.
              [4]  S. Konishi, S. Nishio, K. Tobita, DEMO plant design beyond ITER, Fusion Eng. Des. 63-64
                (2002) 11–17.
              [5]  M. Kwon, Y.-S. Na, J.-H. Han, et al. A strategic plan of Korea for developing fusion energy
                beyond ITER, Fusion Eng. Des. 83 (2008) 883–888.
              [6]  D. Maisonnier, European DEMO design and maintenance strategy, Fusion Eng. Des. 83
                (2008) 858–864.
              [7]  C.H. Pan, Y.C. Wu, K.M. Feng, S.L. Liu, DEMO development strategy based on China FPP
                program, Fusion Eng. Des. 83 (2008) 877–882.
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