Flibe/He concept
As in all fusion blankets many physics and engineering parameters influence material temperature and heat transfer to the coolant. In performing thermal-hydraulics calculations for the Flibe/He concept, the first wall was assumed to be 5 MW/m/sup 2/. The coolant is helium with a nominal pressure of 50 atmospheres. To eliminate ''pinch-point'' steam generator problems a helium inlet temperature of 275/sup 0/C was specified. Helium outlet temperature was limited to 500/sup 0/C in order to not have structural HT-9 steel above 550/sup 0/C. That limit for HT-9 has been imposed due to neutron damage effects which seriously detract from its ductility and strength above that temperature. Volumetric heating calculations at various blanket locations are given.
- Research Organization:
- Lawrence Livermore National Lab., CA (USA)
- DOE Contract Number:
- W-7405-ENG-48
- OSTI ID:
- 5379123
- Report Number(s):
- UCID-20234; ON: DE86014403
- Country of Publication:
- United States
- Language:
- English
Similar Records
The influence of reactor operations on the design and performance of tokamaks with solid-breeder blankets
A performance comparison of lithium, helium, and flibe cooled tube/header fusion blankets
Flibe/Be/He/FS concept (R = 1)
Conference
·
Fri Oct 31 23:00:00 EST 1986
· Fusion Technol.; (United States)
·
OSTI ID:6929735
A performance comparison of lithium, helium, and flibe cooled tube/header fusion blankets
Journal Article
·
Wed Mar 31 23:00:00 EST 1982
· J. Fusion Energy; (United States)
·
OSTI ID:5384596
Flibe/Be/He/FS concept (R = 1)
Technical Report
·
Mon Oct 01 00:00:00 EDT 1984
·
OSTI ID:5841581