Tritium confinement and recovery considerations for Li17P683 fusion blankets
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5119499
None
- Research Organization:
- General Atomic, San Diego, CA 92138
- OSTI ID:
- 5119499
- Report Number(s):
- CONF-811103-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 39
- Country of Publication:
- United States
- Language:
- English
Similar Records
Fissionable blankets for inertial confinement fusion production of tritium
Tritium-tritium fusion: blanket neutronics and photonics
Design considerations for fusion synfuel blankets
Conference
·
Sat Oct 01 00:00:00 EDT 1983
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6998125
Tritium-tritium fusion: blanket neutronics and photonics
Conference
·
Tue Jun 01 00:00:00 EDT 1982
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6825818
Design considerations for fusion synfuel blankets
Conference
·
Mon Dec 31 23:00:00 EST 1979
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6861517
Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700206* -- Fusion Power Plant Technology-- Environmental Aspects
ALLOYS
BREEDING BLANKETS
D-T REACTORS
DESIGN
FIRST WALL
LIQUID METAL COOLED REACTORS
LITHIUM ALLOYS
LITHIUM BASE ALLOYS
LITHIUM COOLED REACTORS
REACTOR COMPONENTS
REACTORS
RECOVERY
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TRITIUM RECOVERY
700206* -- Fusion Power Plant Technology-- Environmental Aspects
ALLOYS
BREEDING BLANKETS
D-T REACTORS
DESIGN
FIRST WALL
LIQUID METAL COOLED REACTORS
LITHIUM ALLOYS
LITHIUM BASE ALLOYS
LITHIUM COOLED REACTORS
REACTOR COMPONENTS
REACTORS
RECOVERY
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TRITIUM RECOVERY