ARIES-ACT1 Safety Design and Analysis

Journal Article · Wed Jan 01 00:00:00 EST 2014 · Fusion Science and Technology

DOI:https://doi.org/10.13182/FST14-799· OSTI ID:1178052

Humrickhouse, Paul W. ^[1]; Merrill, Brad J. ^[1]

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1. Idaho National Lab. (INL), Idaho Falls, ID (United States)

ARIES-ACT1 (Advanced and Conservative Tokamak) is a 1000-MW(electric) tokamak design featuring advanced plasma physics and divertor and blanket engineering. Some relevant features include an advanced SiC blanket with PbLi as coolant and breeder; a helium-cooled steel structural ring and tungsten divertors; a thin-walled, helium-cooled vacuum vessel; and a room-temperature, water-cooled shield outside the vacuum vessel. We consider here some safety aspects of the ARIES-ACT1 design and model a series of design-basis and beyond-design-basis accidents with the MELCOR code modified for fusion. The presence of multiple coolants (PbLi, helium, and water) makes possible a variety of such accidents. We consider here a loss-of-flow accident caused by a long-term station blackout (LTSBO), an ex-vessel helium break into the cryostat, and a beyond-design-basis accident in which a LTSBO is aggravated by a loss-of-coolant accident in ARIES-ACT1's ultimate decay heat removal system, the water-cooled shield. In the design-basis accidents, we find that the secondary confinement boundaries are not challenged, and the structural integrity of in-vessel components is not threatened by high temperatures or pressures; decay heat can be passively removed.

• Research Organization: Idaho National Lab. (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE Office of Science (SC)
• DOE Contract Number: AC07-05ID14517
• OSTI ID: 1178052
• Report Number(s): INL/JOU-13-30976; TRN: US1500189
• Journal Information: Fusion Science and Technology, Vol. 67, Issue 1; ISSN 1536-1055
• Publisher: American Nuclear Society
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
DESIGN BASIS ACCIDENTS
LOSS OF COOLANT
LOSS OF FLOW
HELIUM
SILICON CARBIDES
TOKAMAK DEVICES
DESIGN
CRYOSTATS
TUNGSTEN
TEMPERATURE RANGE 0273-0400 K
TEMPERATURE RANGE 0400-1000 K
REACTOR SAFETY
AFTER-HEAT REMOVAL
COOLANTS
DIVERTORS
SHIELDS
WATER
CONFINEMENT
OUTAGES
LEAD ALLOYS
LITHIUM ALLOYS
ARIES
FUSION
LONG TERM STATION BLACKOUT
LOSS OF COOLANT ACCIDENT
SEVERE ACCIDENTS