Application of the aqueous self-cooled blanket concept to fusion reactors
The development of a reliable, safe, and economically attractive tritium breeding blanket is an essential requirement in the path to commercial fusion power. The primary objective of the recently completed Blanket Comparison and Selection Study (BCSS) was to evaluate previously proposed concepts, and thereby identify a limited number of preferred options that would provide the focus for an R and D program. The water-cooled concepts in the BCSS scored relatively low. We consider it prudent that a promising water-cooled blanket concept be included in this program since nearly all power producing reactors currently rely on water technology. It is in this context that we propose the novel water-cooled blanket concept described herein.
- Research Organization:
- AECL, Chalk River, Ottawa
- OSTI ID:
- 5503752
- Report Number(s):
- CONF-860610-; TRN: 88-008078
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Vol. 52; Conference: American Nuclear Society annual meeting, Reno, NV, USA, 15 Jun 1986
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BREEDING BLANKETS
COOLING
DESIGN
TANDEM MIRRORS
FIRST WALL
LITHIUM
REACTOR COOLING SYSTEMS
TRITIUM
ALKALI METALS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
COOLING SYSTEMS
ELEMENTS
ENERGY SYSTEMS
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
MAGNETIC MIRRORS
METALS
NUCLEI
ODD-EVEN NUCLEI
OPEN PLASMA DEVICES
RADIOISOTOPES
REACTOR COMPONENTS
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR WALLS
YEARS LIVING RADIOISOTOPES
700201* - Fusion Power Plant Technology- Blanket Engineering