Published October 16, 2018 | Version v1
Report

Activity of Indian High Heat Flux Test Facility

  • 1. Institute for Plasma Research (IPR), Bhat, Gandhinagar (India)

Description

Full text: Plasma facing components (PFCs) of ITER-like tokamak are expected to subject high heat loads up to 10 MW/m2 during the tokamak operation in steady state condition. Selection of plasma facing materials/components required extensive qualification and testing for tokamak application. The High Heat Flux Test Facility (HHFTF) plays an important role for the qualification and estimation of the life of the component under defined heat load condition. HHFTF with heat flux generated by an electron beam system having 200 kW power and 45 kV maximum acceleration voltage is in full-fledged operation since 2016. HHFTF is dedicated for high heat flux testing of numerous materials and plasma facing components (small and medium sized) for several thousand thermal cycles at different heat loads. The facility is equipped with high vacuum pumping systems with pressure regulation, high pressure high temperature water circulation loop and several diagnostics devices such as pyrometers, IR-cameras, video cameras, flow, pressure and temperature sensors. This paper describes the main capabilities of the HHFTF and gives a glimpse of various tests performed on plasma facing materials and components. (author)

Part of:
27th IAEA Fusion Energy Conference. Programme and Book of Abstracts

Additional details

Publishing Information

Imprint Title
27th IAEA Fusion Energy Conference. Programme and Book of Abstracts
Imprint Pagination
844 p.
Journal Page Range
p. 157
Report number
IAEA-CN--258

Conference

Title
27. IAEA Fusion Energy Conference
Acronym
FEC 2018
Dates
22-27 Oct 2018
Place
Ahmedabad (India)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
50050343
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ELECTRON BEAMS; FIRST WALL; HEAT FLUX; HEATING LOAD; ITER TOKAMAK; PYROMETERS; STEADY-STATE CONDITIONS; TELEVISION CAMERAS; TEST FACILITIES
Descriptors DEC
BEAMS; CAMERAS; CLOSED PLASMA DEVICES; LEPTON BEAMS; MEASURING INSTRUMENTS; PARTICLE BEAMS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Secondary number(s)
IAEA-CN--258-605