Published 2006 | Version v1
Report

Design, analyses and R and D for EAST in-vessel components

Creators

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

Description

In-vessel components are important parts of EAST superconducting tokamak. It is include plasma facing components, passive plates, cryo-pumps, in-vessel coils, etc. The structure optimized design, analyses and related R and D has been complete. Divertor is up down symmetric to accommodate both double null and single null operation. Passive plates can supply around 100 ms time constant during plasma vertical movements. In-vessel coils are used for plasma vertical movements active control. Each cryo-pumps can supply around 45 m3/s pumping speed for particle exhaust. Analyses shows when 1 MA plasma current disrupt in 3 ms EM loads caused by halo current (Ihalo 25%Ip, TPF=2) will not bring unacceptable stress on divertor structure. Graphite tiles bolted to heat sink. Cooling channel consist of holes on heat sink. The bolted divertor thermal structure can sustain 2 MW/m2 up to 60 s operation if we limited first surface temperature 1500 deg C. Thermal testing and structure optimised testing have been made to demonstrate the analyses result. All the in vessel components are under fabrication and components for first plasma will be complete around July 2006. (author)

Part of:
21. IAEA fusion energy conference. Book of abstracts

Additional details

Publishing Information

Imprint Title
21. IAEA fusion energy conference. Book of abstracts
Imprint Pagination
226 p.
Journal Page Range
p. 198
Report number
IAEA-CN--149

Conference

Title
21. IAEA fusion energy conference
Dates
16-21 Oct 2006
Place
Chengdu (China)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
37110176
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONTAINERS; CONTROL; DESIGN; DIVERTORS; ELECTRIC CURRENTS; FABRICATION; FIRST WALL; GRAPHITE; HEAT SINKS; OPERATION; PLASMA; PUMPS; STRESSES; SUPERCONDUCTING MAGNETS; THERMAL TESTING; TOKAMAK DEVICES
Descriptors DEC
CARBON; CLOSED PLASMA DEVICES; CURRENTS; ELECTRICAL EQUIPMENT; ELECTROMAGNETS; ELEMENTS; EQUIPMENT; MAGNETS; MATERIALS TESTING; MINERALS; NONDESTRUCTIVE TESTING; NONMETALS; SINKS; SUPERCONDUCTING DEVICES; TESTING; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS

Optional Information

Secondary number(s)
FT/P7--7