Thermal-hydraulic design for the lithium-cooled TITAN reversed-field-pinch reactor
Creators
- 1. Univ. of California at Los Angeles, Los Angeles, CA 90024-1597 (USA)
Description
A thermal-hydraulic design of the first wall and blanket of the 18 MW/m2 neutron wall loading TITAN reversed-field-pinch (RFP) fusion reactor using liquid-lithium as coolant and V-3Ti-1Si as structural material is described. The first wall is made of tubes and the blanket coolant channels are a combination of tubular, square and rectangular channels. The coolant channels are aligned with the larger poloidal magnetic field. The first-wall and blanket coolant circuits are separate. Magnetohydrodynamic (MHD) turbulent-flow heat transfer is utilized when the heat flux on the first wall is high, allowing an extension of the design window up to about 5 MW/,m2 heat flux. The coolant velocities are 21 m/s in the first-wall and about 0-.5 m/s in the blanket coolant channels. The corresponding pressure drops are 10 MPa and 3.0 MPa, respectively. The coolant pumping power is about 53 MW which is less than 5% of the electric output. The coolant inlet temperature is 3200C and the exit temperatures are 4400C and 7000C for the first-wall and blanket circuits, respectively. The maximum structure temperature is less than 750C and the material stresses are below the allowable design limits
Additional details
Publishing Information
- Publisher
- IEEE Service Center.
- Imprint Place
- Piscataway, NJ (USA)
- Imprint Title
- Proceedings of the 12th symposium on fusion engineering
- Imprint Pagination
- vp.
- Journal Page Range
- p. 1054-1057.
Conference
- Title
- 12. symposium on fusion engineering.
- Dates
- 12-16 Oct 1987.
- Place
- Monterey, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21016657
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COOLANTS; COOLING SYSTEMS; HYDRAULICS; LITHIUM; MAGNETOHYDRODYNAMICS; REACTOR COOLING SYSTEMS; REVERSE-FIELD PINCH; SPECIFICATIONS; THERMODYNAMICS; TOKAMAK DEVICES
- Descriptors DEC
- ALKALI METALS; CLOSED PLASMA DEVICES; ELEMENTS; FLUID MECHANICS; HYDRODYNAMICS; MECHANICS; METALS; PINCH EFFECT; REACTOR COMPONENTS; THERMONUCLEAR DEVICES
Optional Information
- Secondary number(s)
- CONF-871007--.