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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.