Thermal and hydraulic analysis of the cooling system for the ITER equatorial port plugs (original) (raw)
Related papers
A conceptual design of the ITER upper port plug structure and its cooling channels
Fusion Engineering and Design, 2008
A study is conducted on the conceptual design of the structure and cooling channels of the upper port plug of International Thermonuclear Experimental Reactor (ITER). Modification of the earlier port plug design is made and a simple fabrication method is proposed. It is shown that the newly designed port plug can accommodate the installation of both diagnostic and electron cyclotron heating (ECH) devices. Design assessment is carried out through structural and thermo-hydraulic analyses. Results of the analyses show that the port plug structure is stable against one of the most severe plasma events and the total pressure drop of the coolant is within the allowable level.
Fusion Engineering and Design, 2016
h i g h l i g h t s • The cooling system of the ITER Generic Equatorial Port Plug (GEPP) is of a complicated combination of horizontal and vertical channels. • The calculation model for the entire GEPP cooling circuit comprising 12 sub-circuits and built up of 2421 finite-volume elements has been developed. • Transient analysis of this model simulating the draining procedure by the KORSAR/B1 code has been performed. • Water in amount of 263 g of initial 531 kg in the GEPP remains in the dead-ends of the DSM and DFW channels in 150 s of draining procedure. • Almost 3 h are required to boil off 263 g of water trapped in the dead-ends.
Fusion Science and Technology, 2009
A preliminary thermo-hydraulic analysis was performed on the ITER diagnostic upper port plug. Relevant thermal and hydraulic parameters, such as coolant pressure drop, maximum structure temperature and bake-out time, were calculated for normal operation and baking. The upper port plug considered is based on the preliminary generic structure design of Princeton Plasma Physics Laboratory and the Blanket Shield Module (BSM) developed in Europe. The diagnostic shield modules are modeled so that the Korean diagnostic procurement package, which includes Vacuum UltraViolet (VUV) spectrometer and neutron activation system, can be integrated. The analysis provides design inputs to optimize flow in the cooling channels of the plug. The conjugated heat transfer analysis for the port plug confirms that it is important to secure accurate nuclear heat and accurate electromagnetic (EM) force for the design of the joining flange between the BSM and the main body. Thermal analysis shows that it will take ten hours for the port plug to reach the bake-out temperature (240 o C), if the window plate is heated additionally from the rear side.
ITER diagnostic port plug engineering design analysis in the EU
Fusion Engineering and Design, 2007
Engineering analysis has been carried out on a representative equatorial diagnostic port plug of ITER, outcome of which is given here. A preliminary overview of the work for a prototypical diagnostic upper port plug is also reported. To ensure that the port plug structure satisfies the requirements of the ITER environment, the following analyses have been performed: finite element (FE) analyses of static and dynamic behaviour under electromagnetic loads, FE vibration analysis, FE thermal-structural analysis and nuclear heating and radiation dose studies. The main outcomes from these analyses and consequent design developments are a revision of the stainless steel/water ratio in the plug neutron shielding modules and the incorporation of improved neutron shielding of the port duct, a modification of the port plug top plate arrangement, to increase torsional stiffness of the structure under disruption loads, and improved solutions for cooling arrangements. Manufacturing studies have also been performed, involving the assessment of methods for the production of plug flanges, the analysis of welding techniques for parts assembly and methods for the introduction of cooling features in plug components. Reference design solutions and possible modifications will be presented and discussed.
Progress on the Integration of ITER Diagnostics Equatorial Port Plugs in Europe
IEEE Transactions on Plasma Science, 2000
Diagnostics in ITER are supported by big structures called port plugs, the second main function of which is to ensure a sufficient shielding against neutrons and gammas. Regarding the integration of diagnostics in equatorial port plugs, a new approach is under study, which consists in installing the diagnostics in "drawers". This paper describes the recent work which has been performed in Europe on the integration of diagnostics in drawers in the Equatorial Port Plug 1 (EPPl). First the methodology which has been followed to progress on the integration of the diagnostics in this port plug is described and the resulting arrangement of diagnostics is shown. Then a special attention is paid to the integration of the two main diagnostics of EPPl, namely the visible/infrared wide angle viewing system and the radial neutron camera. Finally the preliminary design of the drawers of EPPl, in particular the shielding modules around the diagnostics, is presented, and the preliminary results of the analyses performed to validate this design are provided.
Design and Analysis Progress of ITER Diagnostic Equatorial Port #09
IEEE Transactions on Plasma Science, 2018
ITER is the world's largest fusion device currently under construction in the South of France with >50 diagnostic systems to be installed inside the port plugs (PPs), the interspace (IS) or the port cell (PC) region of various diagnostic ports. The plasma facing Diagnostic First Wall (DFW) and its supporting diagnostic shield modules (DSM) are designed to protect frontend diagnostics from plasma neutron and plasma radiation while providing apertures for diagnostic access to the plasma. The design of ITER port plug structures (PPS) including the DFW and the DSM is largely driven by the electromagnetic (EM) loads included on the PP structural components during plasma major disruptions (MDs) and the vertical displacement events (VDEs). Unlike DFW and DSM, the design of diagnostic system, however, is likely driven by the steady-state thermal loads from plasma volumetric and surface heating and the dynamic response of the in-port components attached to the port-specific DSM or closure plate under transient loads induced on the Vacuum Vessel (VV) and the port extension during asymmetric VDEs. Three tenant diagnostic systems are integrated into the equatorial port 09 (E09). The toroidal interferometer / polarimeter, or TIP system, is installed in the left drawer (DSM3, left looking from plasma) for measuring the plasma density so to control the fuel input. The electron cyclotron emission (ECE) system is installed in the middle drawer (DSM2) to provide the high spatial and temporal resolution measurements of electron temperature evolution and the electron thermal transport inferences. The visible/infrared wide angle viewing system is installed in the right drawer (DSM1) to provide visible and infra-red viewing and temperature data of the first wall for its protection in support of machine operation. The port plug integration design and multi-physics analyses are performed following port integration requirements including the weight limit (45 tones total), shut down dose rate limits, the cooling / heating and structural integrity validation. Mass distribution for TIP and ECE DSMs has been optimized to minimize the total weight by a new design of the boron carbide (B4C) shielding pocket. The lightened DSM maintains its frontend load distribution and the structural stiffness with minimum impact to the DFW so to better protect on-board diagnostics; while still provides sufficient front end stiffness for its structural integrity as well as the diagnostics function requirements.
Final design of the generic upper port plug structure for ITER diagnostic systems
Fusion Engineering and Design, 2016
The generic upper port plug (GUPP) structure in ITER is a 6 m long metal box which deploys diagnostic components into the vacuum vessel. This structure is commonly used for all the diagnostic upper ports. The final design of the GUPP structure, which has successfully passed the final design review in 2013, is described here.
Results of an integration study of a diagnostics port plug in ITER
Fusion Engineering and Design, 2013
h i g h l i g h t s An extensive study on the integration of diagnostics in a port plug of ITER has been performed. It has shown that the diagnostic performances could not be reached if their number was not decreased. A design of Diagnostic Shield Modules has been validated through mechanical and thermal analyses. These analyses have confirmed that the highest loads are concentrated in the vicinity of the plasma.
Numerical simulation on bake-out of the ITER diagnostic upper port plug
Fusion Engineering and Design, 2010
The diagnostic upper port plug in ITER is fixed to the upper port of the vacuum vessel as a cantilevered beam with bolts and forms a primary vacuum boundary. It needs to be baked out for outgassing before normal operation. This study calculated the required bake-out time and the transient thermal stress during baking for the diagnostic upper port plug. The calculation was done through numerical simulation. The analysis took into consideration the gradual temperature increase of working fluid. In order to look into the effect of radiation heat transfer from the upper port plug to the vacuum vessel port, the upper vacuum vessel port was included in this analysis.