Divertor for use in fusion reactors
Patent
·
OSTI ID:863326
A poloidal divertor for a toroidal plasma column ring having a set of poloidal coils co-axial with the plasma ring for providing a space for a thick shielding blanket close to the plasma along the entire length of the plasma ring cross section and all the way around the axis of rotation of the plasma ring. The poloidal coils of this invention also provide a stagnation point on the inside of the toroidal plasma column ring, gently curving field lines for vertical stability, an initial plasma current, and the shaping of the field lines of a separatrix up and around the shielding blanket.
- Research Organization:
- Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)
- Sponsoring Organization:
- US Atomic Energy Commission (AEC)
- DOE Contract Number:
- AT(11-1)-3073
- Assignee:
- United States of America as represented by United States (Washington, DC)
- Patent Number(s):
- 4,149,931
- Application Number:
- 05/379870
- OSTI ID:
- 863326
- Resource Relation:
- Patent File Date: 1973 Jul 16
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
divertor
fusion
reactors
poloidal
toroidal
plasma
column
set
coils
co-axial
providing
space
thick
shielding
blanket
close
entire
length
section
axis
rotation
provide
stagnation
inside
gently
curving
field
lines
vertical
stability
initial
current
shaping
separatrix
fusion reactors
poloidal divertor
plasma current
field lines
plasma column
entire length
toroidal plasma
fusion reactor
vertical stability
poloidal coil
/376/
fusion
reactors
poloidal
toroidal
plasma
column
set
coils
co-axial
providing
space
thick
shielding
blanket
close
entire
length
section
axis
rotation
provide
stagnation
inside
gently
curving
field
lines
vertical
stability
initial
current
shaping
separatrix
fusion reactors
poloidal divertor
plasma current
field lines
plasma column
entire length
toroidal plasma
fusion reactor
vertical stability
poloidal coil
/376/