The cooling test platform design for iter radial x-ray camera
Creators
- 1. University of Science and Technology of China, Hefei, 230026 (China)
- 2. Institute of Plasma Physics Chinese Academy of Sciences, Hefei, 230031 (China)
Description
Highlights: • A cooling test platform is developed in order to meet the cooling requirement of ITER RXC. • The architecture and heat transfer capacities of the cooling test platform are analyzed. • A Data Acquisition (DAQ) system is developed based on Experimental Physics and Industrial Control System (EPICS) framework. • Experimental results showed that with 0.003m3/s inlet helium flow, detectors' temperature can be controlled under 75℃ while baking temperature is 250℃ in the cooling testing system. - Abstract: The Radial X-ray Camera (RXC) is a diagnostic in Equatorial Port 12 (EQ#12) of International Thermonuclear Experimental: Reactor (ITER). Normally, the operating temperature of detector on RXC system shall be lower than 75 °C. But the detectors on some part of RXC system will have to face a high temperature of 250 °C during baking of ITER, as a result of which case detectors will be easily damaged. Due to the harsh environment, cooling for RXC system is necessary. In order to verify the effect of gas cooling, the related research and experiments are being carried out. This article focuses on the analysis of the architecture and heat transfer capacities of the cooling test platform. According to the analysis results, the solution of the cooling platform is introduced and a cooling test platform is established. Also, a Data Acquisition (DAQ) system is developed based on Experimental Physics and Industrial Control System (EPICS) framework. The experiment results based on the cooling test platform provide support for the cooling system design of RXC system.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2018.01.057Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2018.01.057;
- PII
- S0920379618300759;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 128
- Journal Page Range
- p. 163-167
- ISSN
- 0920-3796
- CODEN
- FEDEEE
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51012084
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- CAMERAS; CONTROL SYSTEMS; COOLING SYSTEMS; DATA ACQUISITION; EXPERIMENTAL REACTORS; GAS COOLING; HEAT TRANSFER; HELIUM; ITER TOKAMAK; SUPPORTS; X RADIATION
- Descriptors DEC
- CLOSED PLASMA DEVICES; COOLING; DATA PROCESSING; ELECTROMAGNETIC RADIATION; ELEMENTS; ENERGY SYSTEMS; ENERGY TRANSFER; FLUIDS; GASES; IONIZING RADIATIONS; MECHANICAL STRUCTURES; NONMETALS; PROCESSING; RADIATIONS; RARE GASES; REACTORS; RESEARCH AND TEST REACTORS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Notes
- © 2018 Elsevier B.V. All rights reserved.