Molten salt cooling//sup 17/Li-/sup 83/Pb breeding blanket concept
Conference
·
OSTI ID:5857826
A description of a fusion breeding blanket concept using draw salt coolant and static /sup 17/Li-/sup 83/Pb is presented. /sup 17/Li-/sup 83/Pb has high breeding capability and low tritium solubility. Draw salt operates at low pressure and is inert to water. Corrosion, MHD, and tritium containment problems associated with the MARS design are alleviated because of the use of a static LiPb blanket. Blanket tritium recovery is by permeation toward the plasma. A direct contact steam generator is proposed to eliminate some generic problems associated with a tube shell steam generator.
- Research Organization:
- Argonne National Lab., IL (USA); GA Technologies, Inc., San Diego, CA (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5857826
- Report Number(s):
- CONF-850310-74; ON: DE85010522
- Country of Publication:
- United States
- Language:
- English
Similar Records
A molten salt cooling 17Li-83Pb breeding blanket concept
Tritium breeding benchmark calculations for a Li/sub 17/Pb/sub 83/ blanket with steel structure
In-situ tritium recovery from Li/sub 17/Pb/sub 83/ breeding blanket
Conference
·
Mon Jul 01 00:00:00 EDT 1985
· Fusion Technol.; (United States)
·
OSTI ID:5794010
Tritium breeding benchmark calculations for a Li/sub 17/Pb/sub 83/ blanket with steel structure
Journal Article
·
Sat Sep 01 00:00:00 EDT 1984
· Fusion Technol.; (United States)
·
OSTI ID:5539322
In-situ tritium recovery from Li/sub 17/Pb/sub 83/ breeding blanket
Conference
·
Wed Dec 31 23:00:00 EST 1980
· Proc. Symp. Eng. Probl. Fusion Res.; (United States)
·
OSTI ID:6361378