First-wall structural analysis of the self-cooled water blanket concept

Conference · Wed Jan 01 04:00:00 EST 1986 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:5577548

O'Brien, D A; Steiner, D; Embrechts, M J

A novel blanket concept recently proposed utilizes water with small amounts of dissolved lithium compound as both coolant and breeder. The inherent simplicity of this idea should result in an attractive breeding blanket for fusion reactors. In addition, the available base of relevant information accumulated through water-cooled fission reactor programs should greatly facilitate the R and D effort required to validate this concept. First-wall and blanket designs have been developed first for the tandem mirror reactor (TMR) due to the obvious advantages of this geometry. First-wall and blanket designs will also be developed for toroidal reactors. A simple plate design with coolant tubes welded on the back (side away from plasma) was chosen as the first wall for the TMR application. Dimensions and materials were chosen to minimize temperature differences and thermal stresses. A finite element code (STRAW), originally developed for the analysis of core components subjected to high-pressure transients in the fast breeder program, was utilized to evaluate stresses in the first wall.

• OSTI ID: 5577548
• Report Number(s): CONF-860610-
• Conference Information: Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 52
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
ALKALI METALS
BREEDING BLANKETS
COMPUTER CODES
COOLING SYSTEMS
ELEMENTS
ENERGY SYSTEMS
FINITE ELEMENT METHOD
FIRST WALL
HYDROGEN COMPOUNDS
LITHIUM
MAGNETIC MIRROR TYPE REACTORS
MECHANICAL PROPERTIES
METALS
NUMERICAL SOLUTION
OXYGEN COMPOUNDS
REACTOR COMPONENTS
S CODES
STRESSES
THERMONUCLEAR REACTOR COOLING SYSTEMS
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TMR REACTORS
WATER