ORNL facilities for testing first-wall components
Future long-impulse magnetic fusion devices will have operating characteristics similar to those described in the design studies of the Tokamak Fusion Core Experiment (TFCX), the Fusion Engineering Device (FED), and the International Tokamak Reactor (INTOR). Their first-wall components (pumped limiters, divertor plates, and rf waveguide launchers with Faraday shields) will be subjected to intense bombardment by energetic particles exhausted from the plasma, including fusion products. These particles are expected to have particle energies of approx.100 eV, particle fluxes of approx.10/sup 18/ cm/sup -2/.s/sup -1/, and heat fluxes of approx.1 kW/cm/sup 2/ CW to approx.100 kW/cm/sup 2/ transient. No components are available to simultaneously handle these particle and heat fluxes, survive the resulting sputtering erosion, and remove exhaust gas without degrading plasma quality. Critical issues for research and development of first-wall components have been identified in the INTOR Activity. Test facilities are needed to qualify candidate materials and develop components. At Oak Ridge National Laboratory (ORNL), existing neutral beam and wave heating test facilities can be modified to simulate first-wall environments with heat fluxes up to 30 kW/cm/sup 2/, particle fluxes of approx.10/sup 18/ cm/sup -2/.s/sup -1/, and pulse lengths up to 30 s, within test volumes up to approx.100 L. The characteristics of these test facilities are described, with particular attention to the areas of particle flux, heat flux, particle energy, pulse length, and duty cycle, and the potential applications of these facilities for first-wall component development are discussed.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6413996
- Report Number(s):
- CONF-851102-58; ON: DE86004793
- Resource Relation:
- Conference: 11. symposium on engineering problems in fusion research, Austin, TX, USA, 18 Nov 1985; Other Information: Paper copy only, copy does not permit microfiche production
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
THERMONUCLEAR REACTOR WALLS
TESTING
TOKAMAK TYPE REACTORS
DIVERTORS
HEAT FLUX
INTOR TOKAMAK
NEUTRON FLUX
PUMPED LIMITERS
TEST FACILITIES
TFCX REACTORS
LIMITERS
RADIATION FLUX
THERMONUCLEAR REACTORS
700209* - Fusion Power Plant Technology- Component Development & Materials Testing