Published 2017 | Version v1
Report

Failure analysis of EAST Lower divertor

  • 1. Institute of Plasma Physics, Chinese Academy of Science (China)

Description

Full text: Experimental Advanced Superconducting Tokamak (EAST) has equipped the lower divertor since 2008. Lower divertor comprises total 2952 graphite tiles, 96 heat sinks and 48 support frames. With the length of plasma pulse in H-mode reached 100s thermal power deposited on the divertor has become very larger. Lots of hot spots had been observed on the lower divertor while plasma discharge. During plasma discharge tens graphite tiles damaged and a lot of dust of carbon made the plasma quench at last. By the analysis there are three main failure modes for graphite tiles: crack, erosion and release. A few graphite tiles cracked into two or three pieces and most graphite tiles had been erosion on the corners, edges and front surfaces. Some graphite tiles have no any damage on them but their position changed. Here the damage process has been researched by simulation and experiments to find the failure mechanism. Most failures are because of overheating. When the high heat flux on anywhere of graphite tiles expired the limits of lower divertor the erosion occurred some failures are because of electromagnetic force. When electromagnetic force on the graphite tiles was larger than the strength of graphite the crack occurred. Other failures are because of both thermal power and electromagnetic force. When the graphite tiles were heating the preload to mount the tiles reduced largely. The electromagnetic force would pull or push tiles to make the position of graphite tiles changed again and again and then they became released from heat sink. The failure analysis here helped to realize the performance limits of EAST lower divertor and helped to optimize or upgrade it in future. (author)

Part of:
2nd IAEA Technical Meeting Divertor Concepts. Programme and Book of Abstracts

Additional details

Publishing Information

Imprint Title
2nd IAEA Technical Meeting Divertor Concepts. Programme and Book of Abstracts
Imprint Pagination
80 p.
Journal Page Range
p. 67
Report number
INIS-XA--21M3794

Conference

Title
2. IAEA Technical Meeting on Divertor Concepts
Acronym
DC 2017
Dates
13-16 Nov 2017
Place
Suzhou (China)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
52124488
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTERIZED SIMULATION; DIVERTORS; EROSION; GRAPHITE; HEAT FLUX; HEAT SINKS; HEATING; H-MODE PLASMA CONFINEMENT; HOT SPOTS; HT-7U TOKAMAK; PERFORMANCE; PLASMA; PULSES; SURFACES
Descriptors DEC
CARBON; CLOSED PLASMA DEVICES; CONFINEMENT; ELEMENTS; MAGNETIC CONFINEMENT; MINERALS; NONMETALS; PLASMA CONFINEMENT; SIMULATION; SINKS; THERMONUCLEAR DEVICES; TOKAMAK DEVICES

Optional Information