Passive decay heat removal in liquid-metal-cooled reactors

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

OSTI ID:5637852

Malinovic, B; Kazimi, M

The use of liquid-metal, self-cooled blankets in fusion reactors could offer desirable thermal and mechanical characteristics. This study has considered the response of such blankets to a loss-of-flow accident (LOFA) where reactor afterheat is removed via natural convection alone. The coolant temperature rise through the blanket for such an event was determined and compared to the temperature rise for normal operation. This study defined primary flow loops for tokamak and tandem mirror reactor (TMR) designs by using Argonne National Laboratory's Blanket Comparison and Selection Study to obtain blanket designs, and by using the STARFIRE and MARS works as reactor reference designs.

• Research Organization: Massachusetts Institute of Technology, Cambridge
• OSTI ID: 5637852
• Report Number(s): CONF-860610-; TRN: 88-008107
• 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

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
THERMONUCLEAR REACTOR COOLING SYSTEMS
LOSS OF FLOW
THERMONUCLEAR REACTORS
BREEDING BLANKETS
AFTER-HEAT REMOVAL
LEAD ALLOYS
LIQUID METALS
LITHIUM ALLOYS
MAGNETOHYDRODYNAMICS
PRESSURE DROP
REACTOR SAFETY
ACCIDENTS
ALLOYS
COOLING SYSTEMS
ELEMENTS
ENERGY SYSTEMS
FLUID MECHANICS
FLUIDS
HYDRODYNAMICS
LIQUIDS
MECHANICS
METALS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REMOVAL
SAFETY
700201* - Fusion Power Plant Technology- Blanket Engineering
700204 - Fusion Power Plant Technology- Cooling Systems
700206 - Fusion Power Plant Technology- Environmental Aspects