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Title: ARIES-ACT1 Safety Design and Analysis

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.
Authors:
 [1] ;  [1]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Publication Date:
OSTI Identifier:
1178052
Report Number(s):
INL/JOU--13-30976
Journal ID: ISSN 1536-1055; TRN: US1500189
DOE Contract Number:
AC07-05ID14517
Resource Type:
Journal Article
Resource Relation:
Journal Name: Fusion Science and Technology; Journal Volume: 67; Journal Issue: 1
Publisher:
American Nuclear Society
Research Org:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Org:
USDOE Office of Science (SC)
Country of Publication:
United States
Language:
English
Subject:
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