Thermal and Hydraulic Analysis of the ITER Upper Vertical Stabilization Coil
Creators
- 1. School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 230027 (China)
- 2. Institute of Plasma Physics, Chinese Academy of Sciences, Hefei 200031 (China)
Description
The ITER upper vertical stabilization (VS) coil is a part of the ITER in-vessel coil (IVC) system, which has the abilities of restraining edge localized modes (ELMs) and maintaining plasma vertical stability. Preliminary structural analysis of the coil has revealed serious thermal stress problems. Due to the very restricted geometry space, it is necessary to perform detailed analysis on thermal and hydraulic characteristics to help optimal design of the coil. It will focus on the temperature distribution and energy balance, as well as some key factors, such as the coolant flow state and surface emissivity, which have influences on the coil performance. The APDL code and some hand calculations are employed in the analysis. The results show that the coolant convection can effectively take away the heat deposited in the coil. But improving the coolant flow state can hardly mitigate the peak temperature occurring at the edges of coil attachments, which are located far away from the coolant. Thermal radiation was expected to be a good method of cooling down these parts. But the reality is not so optimistic since it usually contributes little in the whole energy balance. However, the effect of thermal radiation will become remarkable when bad scenarios or accidents take place. Poor radiation performance of the coil will result in a potential safety hazard. (fusion engineering)
Availability note (English)
Available from http://dx.doi.org/10.1088/1009-0630/16/7/13Additional details
Identifiers
Publishing Information
- Journal Title
- Plasma Science and Technology
- Journal Volume
- 16
- Journal Issue
- 7
- Journal Page Range
- p. 706-711
- ISSN
- 1009-0630
INIS
- Country of Publication
- China
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 46058661
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- CONVECTION; COOLANTS; DESIGN; EDGE LOCALIZED MODES; EMISSIVITY; ITER TOKAMAK; PLASMA; SAFETY; STABILIZATION; TEMPERATURE DISTRIBUTION; THERMAL HYDRAULICS; THERMAL RADIATION; THERMAL STRESSES
- Descriptors DEC
- CLOSED PLASMA DEVICES; ELECTROMAGNETIC RADIATION; ENERGY TRANSFER; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; INSTABILITY; MASS TRANSFER; MECHANICS; OPTICAL PROPERTIES; PHYSICAL PROPERTIES; PLASMA INSTABILITY; PLASMA MACROINSTABILITIES; RADIATIONS; STRESSES; SURFACE PROPERTIES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS