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16     Fundamentals of Magnetic Thermonuclear Reactor Design



              TABLE 2.2 Parameters of Tokamak Reactors Developed in the USSR [4]
                                         T-20      GTRT        OTR
              Parameter                  (1974)    (1978)      (1983–86)
              Nuclear reaction type      Fusion    Fusion–fission  Fusion–fission
              Plasma major radius (m)    5.0       6.4         6.3
              Plasma minor radius (m)    1.75      1.5         1.5
              Aspect ratio               2.8       4.3         4.2
              Elongation of plasma column   1.0    2.0         1.5
              cross-section
              Toroidal magnetic field on plasma   3.7  6.0     5.8
              axis (T)
              Plasma current (MA)        5         4           8
              Stability margin q         2.8       3.0         2.4
              Plasma toroidal beta (%)   3.0       2.8         2.7
              Plasma energy confinement time (s)  2.0  0.8     3.7
              Average plasma temperature (keV)  10  15         8
                                 20
                                    −3
              Average D–T ion density (10  m )  0.5  0.8       1.4
              Thermonuclear power (MW)   ∼200      ∼2000       490
              Total nuclear power generation (MW)  ∼200  7700  750
              Electric power (gross) (MW)  –       2000        300
              Plasma additional heating power   50–60  200     80
              (MW)
                                   2
              Neutron first wall load (MW/m )  0.2  1.0        1.2
              Burn time (s)              15        900         600




            magnetic coils and burn pulse duration within 15 s. In the OTR (Russian ac-
            ronym for experimental fusion reactor) design  [4–7], the burn pulse is lon-
            ger (600 s) than in ITER, the plasma column has an elongated cross-section
            (k = 1.5), and a superconducting magnetic system is employed. OTR is a hybrid
            fusion–fission tokamak reactor with experimental uranium blanket modules that
            enable a thermal power increase from ∼500 to ∼750 MW and generation of
            300 MW(e).
               The GTRT (Russian abbreviation for hybrid fusion tokamak reactor) project
            [4,7] was equipped with all the systems required for FPP operation. The ura-
            nium blanket was expected to help to raise the thermal power from ∼2 GW (for
            plasma-derived heat) to ∼7.7 GW (for the blanket heat) and to obtain around
            2 GW(e) (gross) in the energy transformation system. The reactor’s own power
            consumption was estimated as 700 MW.
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