Design of a stainless-steel helium-cooled first-wall for a tokamak reactor blanket
Description
This report summarizes the results of the thermal and hydraulic analysis on a magnetic fusion power reactor first-wall design that will be tolerant to minor coolant leaks. The design uses stainless steel as a structural material, liquid lithium as a heat conduction and tritium breeding material, and high pressure helium as a coolant. Bubbles of helium from minor leaks float to the surface of the liquid lithium where the gas is pumped off by a vacuum pump. The wall design is capable of absorbing heat flux densities up to 1.0 MW/m2 with the first-wall temperature not exceeding 4500C and the helium pumping power not exceeding 5% of the first wall thermal output. The performance characteristic curves which are developed provide a good basis for comparing first-wall designs
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01.
Files
Additional details
Publishing Information
- Imprint Pagination
- 38 p.
- Report number
- WFPS-TME--79-031
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 13662925
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- COOLANTS; COOLING SYSTEMS; FIRST WALL; HELIUM; HIGH TEMPERATURE; HYDRAULICS; LITHIUM; SPECIFICATIONS; STAINLESS STEELS; THERMODYNAMIC PROPERTIES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES
- Descriptors DEC
- ALKALI METALS; ALLOYS; CARBON ADDITIONS; CHROMIUM ALLOYS; CLOSED PLASMA DEVICES; CORROSION RESISTANT ALLOYS; ELEMENTS; IRON ALLOYS; IRON BASE ALLOYS; METALS; NONMETALS; PHYSICAL PROPERTIES; RARE GASES; STEELS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; TRANSITION ELEMENT ALLOYS