Tokamak experimental power reactor
Abstract
A Tokamak experimental power reactor designed to operate at net electrical power conditions with a plant capacity factor of 50 percent for 10 yrs operates in a pulsed mode at a frequency of approximately 1/min, with approximately 75 percent duty cycle, and is capable of producing approximately 72 MWe. Annual tritium consumption is 16 kg. The stainless steel vacuum chamber has beryllium coated coolant panels mounted on the interior and is surrounded by a stainless steel blanket and shield. The coolant is H20. Sixteen niobium-titanium superconducting toroidal field coils provide a field of 10 T at the coil and 4.47 at the plasma. Plasma current is driven by superconducting ohmic heating and equilibrium field coils. Plasma heating is accomplished by 12 neutral beam injectors which provide 60 MW. The energy transfer and storage system consists of a central superconducting storage ring, a homopolar energy storage unit, and a variety of inductor-convertors.
- Publication:
-
ASME Numerical/Laboratory Computer Methods in Fluid Mechanics
- Pub Date:
- December 1976
- Bibcode:
- 1976asme.meetR....S
- Keywords:
-
- Nuclear Power Plants;
- Reactor Design;
- Reactor Materials;
- Tokamak Devices;
- Cost Analysis;
- Niobium;
- Plasma Heating;
- Reactor Technology;
- Superconducting Magnets;
- Tritium;
- Plasma Physics