Passively safe tandem mirror fusion blanket afterheat thermal analysis

Conference · Thu Jan 01 04:00:00 EST 1987

OSTI ID:5825033

Garner, J K; Carson, C F; Whitley, R H; Gordon, J D

This paper presents results of the thermal analysis of an inherently safe blanket design concept. The blanket is composed of V-15Cr-5Ti structure with lithium for tritium breeding, beryllium for neutron multiplication and SiC for neutron reflection and moderation. Cooling of the blanket is provided by flowing helium gas which is assumed to be unavailable for heat transfer during the accident. The blanket afterheat temperature response was calculated using the SINDA thermal analysis code. Afterheat source values were calculated separately and input as spacially and time varying quantities for each blanket zone. Results indicate that the first wall temperature will peak at 709/sup 0/C in about 1 1/2 days and that the blanket will reach 760/sup 0/C in one year. Any cooling, by convection to the reactor building atmosphere, for example, will reduce these temperatures. Our analysis indicates that this blanket can be left unattended and uncooled at shutdown.

• OSTI ID: 5825033
• Report Number(s): CONF-861211-
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
ACCIDENTS
ALLOY SYSTEMS
ALLOYS
BREEDING
BREEDING BLANKETS
CHROMIUM ALLOYS
COMPUTER CODES
CONVECTION
COOLING
DESIGN
ENERGY TRANSFER
HEAT TRANSFER
HEATING
HIGH TEMPERATURE
MAGNETIC MIRRORS
MASS TRANSFER
NUCLEAR FUEL CONVERSION
OPEN PLASMA DEVICES
PLANNING
REACTOR ACCIDENTS
REACTOR COMPONENTS
RECOVERY
S CODES
SHUTDOWNS
TANDEM MIRRORS
TERNARY ALLOY SYSTEMS
THERMAL ANALYSIS
THERMODYNAMICS
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
TIME DEPENDENCE
TITANIUM ALLOYS
TRITIUM RECOVERY
VANADIUM ALLOYS
WALLS