Published 2017 | Version v1
Report

The Engineering Design of EAST Lower Advanced Divertor

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

Description

In the next 3-4 years, the objective of EAST Tokamak is to achieve longer pulse more than 400s H-mode plasma. So the divertor system of EAST shall accommodate the high heat flux up to 10MW/m2 on the divertor target. The upper divertor now is tungsten divertor with mono-blocks structure. But the lower divertor of EAST is still carbon divertor, which can only endure heat flux up to 2MW/m2 . So the lower divertor shall be updated to fit such heat load. To get snowflake and others advanced divertor shapes, three divertor coils are configured under the lower divertor. The whole lower divertor is divided into 48 modules. Each module is composed of an inner target plate, a Dome, an outer horizontal target plate and an outer vertical baffle plate. To minimize the total mass flow of the cooling system, all these plate are serially connected. To optimize the heat removal capacity of the cooling structure and cooling pipe system of the lower divertor, several types of cooling structures and cooling water distribution systems are considered. Through thermal analysis, fluid analysis and results comparison, the potential final cooling system is determined.

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. 71
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
52124492
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BAFFLES; CARBON; COOLING; COOLING SYSTEMS; DESIGN; DIVERTORS; HEAT; HEAT FLUX; HEATING LOAD; H-MODE PLASMA CONFINEMENT; HT-7U TOKAMAK; PLASMA; PLATES; PULSES; THERMAL ANALYSIS; TUNGSTEN; WATER SUPPLY
Descriptors DEC
CLOSED PLASMA DEVICES; CONFINEMENT; CONTROL EQUIPMENT; ELEMENTS; ENERGY; ENERGY SYSTEMS; EQUIPMENT; FLOW REGULATORS; MAGNETIC CONFINEMENT; METALS; NONMETALS; PLASMA CONFINEMENT; REFRACTORY METALS; THERMONUCLEAR DEVICES; TOKAMAK DEVICES; TRANSITION ELEMENTS

Optional Information