Safety in the ARIES Tokamak Design Study
- EG and G Idaho, Inc., Idaho Falls, ID (USA)
Safety is one of the primary goals of the ARIES Tokamak Design Study. Public safety goals are the achievement passive safety which is demonstrable in tests that could precede operation and the assurance that releases from accidents be passively limited such that no evacuation plan in necessary. Strategies for safety of the plant investment are factory fabrication, short construction times and a design such that no off-normal operational transient results in damage which could not be repaired in routine maintenance. ARIES-I, the first of three visions' of potential tokamak reactors, will use He at 5 MPa as a blanket coolant and SiC/composite ceramic for the first wall and blanket materials. Both the coolant and the structural material were chosen for their low activation, both in the short term after accidents and for long term waste management. The breeder, Li{sub 4}SiO{sub 4}, was also chosen for low activation. Contemporary plasma physics and aggressive technology are used in ARIES-I, which results in very high toroidal fields (24 T maximum at the coil). The stored TF energy will be about 130 GJ. A central concern is the safe discharge of this stored energy under electrical fault conditions and prevention of a failure in the magnet set from propagating into systems containing radioactive inventories. The TF coil system consists of 16 coils, each containing two separate windings powered by two independent power supplies. Arcs and shorts between the two power supply systems and across individual windings have been modeled. In addition, delay or failure in circuit breaker opening has been modeled. The safety impacts of LOCA, LOFA and disruptive events have also been evaluated. 8 refs., 4 figs., 7 tabs.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls, ID (United States)
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- AC07-76ID01570; AC03-89ER52153
- OSTI ID:
- 5393509
- Report Number(s):
- EGG-M-89208; CONF-891007-42; ON: DE90002040; TRN: 89-029046
- Resource Relation:
- Conference: 13. international symposium on fusion engineering, Knoxville, TN (USA), 2-6 Oct 1989
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
TOKAMAK DEVICES
SAFETY ENGINEERING
BREEDING BLANKETS
DESIGN
LITHIUM OXIDES
REACTOR SAFETY
SUPERCONDUCTING MAGNETS
TRANSIENTS
ALKALI METAL COMPOUNDS
CHALCOGENIDES
CLOSED PLASMA DEVICES
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
ENGINEERING
EQUIPMENT
LITHIUM COMPOUNDS
MAGNETS
OXIDES
OXYGEN COMPOUNDS
REACTOR COMPONENTS
SAFETY
SUPERCONDUCTING DEVICES
THERMONUCLEAR DEVICES
700206* - Fusion Power Plant Technology- Environmental Aspects