ITER Korea

Yuseong gu, South Korea

ITER Korea

Yuseong gu, South Korea
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Simrock S.,ITER Organization | Abadie L.,ITER Organization | Barnsley R.,ITER Organization | Bauvir B.,ITER Organization | And 28 more authors.
Fusion Engineering and Design | Year: 2015

ITER requires extensive diagnostics to meet the demands for machine operation, protection, plasma control and physics studies. The interfaces between plant instrumentation and control (I&C) and the central control system follow mandatory rules described in the Plant Control Design Handbook (PCDH) [1], while the design strategy for PCDH compliant plant I&C is covered in its guidelines and supported by hardware catalogues. During preliminary and final design review as well as factory and site acceptance testing it is therefore important to determine the maturity of the I&C design and its implementation to ensure its compliance with the PCDH and the diagnostics performance requirements. © 2015 Elsevier B.V.

De Bock M.F.M.,ITER Organization | Barnsley R.,ITER Organization | Bassan M.,ITER Organization | Bertalot L.,ITER Organization | And 24 more authors.
Journal of Instrumentation | Year: 2016

The ITER tokamak requires diagnostics that on the one hand have a high sensitivity, high spatial and temporal resolution and a high dynamic range, while on the other hand are robust enough to survive in a harsh environment. In recent years significant progress has been made in addressing critical challenges to the development of spectroscopic (but also other) diagnostics. This contribution presents an overview of recent achievements in 4 topical areas: • First mirror protection and cleaning • Nuclear confinement • Radiation mitigation strategy for optical and electronic components • Calibration strategies. © 2016 ITER Organization.

Lee D.W.,Korea Atomic Energy Research Institute | Yum S.B.,Korea Atomic Energy Research Institute | Park G.C.,Seoul National University | Kim S.H.,Pohang University of Science and Technology | And 4 more authors.
Fusion Science and Technology | Year: 2013

The design scheme and system codes for fusion application have been developed for the ITER Test Blanket Module (TBM) program in Korea in parallel with the breeding blanket development, which were based on the developed system codes in Gen. IV reactor development projects such as MARS (Multi-dimensional Analysis of Reactor Safety) and GAMMA (GAs Multicomponent Mixture Analysis). Considering the unique and common features with both the Fusion and Gen. IV reactors, four approaches have been carried out: (1) modifying the heat transfer model and suggesting a 3D analysis for considering the one-sided heating with extreme temperature differences, (2) implementing a tritium permeation model for a simulation of its behavior and amount simulation in a fusion coolant system, (3) developing a physical properties generation model for PbLi and Li considering the liquid metal breeders in these codes, and (4) implementing the magnetohydrodynamics (MHD) model by Miyazaki To integrate these separate codes into single ones, called MARS-FR (Fusion Reactor) and GAMMA-FR, their environments were carefully handled during their development procedure.

Nam K.O.,ITER Korea | Park H.K.,ITER Korea | Kim D.J.,ITER Korea | Ahn H.J.,ITER Korea | And 4 more authors.
Fusion Engineering and Design | Year: 2011

The ITER Tokamak assembly tools are purpose-built assembly tools to complete the ITER Tokamak machine which includes the cryostat and the components contained therein. The sector sub-assembly tools descried in this paper are main assembly tools to assemble vacuum vessel, thermal shield and toroidal filed coils into a complete 40° sector. The 40° sector sub-assembly tools are composed of sector sub-assembly tool, including radial beam, vacuum vessel supports and mid-plane brace tools. These tools shall have sufficient strength to transport and handle heavy weight of the ITER Tokamak machine reached several hundred tons. Therefore these tools should be designed and analyzed to confirm both the strength and structural stability even in the case of conservative assumptions. To verify structural stabilities of the sector sub-assembly tools in terms of strength and deflection, ANSYS code was used for linear static analysis. The results of the analysis show that these tools are designed with sufficient strength and stiffness. The conceptual designs of these tools are briefly described in this paper also. © 2011 Elsevier B.V. All rights reserved.

Im K.,ITER Organization | Shaw R.L.,ITER Organization | Lee J.-H.,SFA Engineering Co. | Kim K.-K.,SFA Engineering Co. | And 4 more authors.
Fusion Engineering and Design | Year: 2011

The conceptual design of the purpose-built assembly tools required for ITER tokamak assembly is given. The ITER machine assembly is sub-divided into five major activities: lower cryostat, sector sub-assembly, sector assembly, ex-vessel, and in-vessel [1]. The core components, vacuum vessel (VV) and toroidal field coil (TFC), are assembled from nine 40° sub-assemblies, each comprising a 40° VV sector, two TFCs, and the associated VV thermal shield (VVTS). The lower cryostat activities must be completed prior to sector assembly in pit to prepare the foundations for the core components, and to locate the lower components to be trapped once the core components installation begins. In-vessel and ex-vessel activities follow completion of sector assembly. To perform these assembly activities requires both massive, purpose-built tools, and standard heavy handling and support tools. The tools have the capability of supporting and adjusting the largest of the ITER components; with maximum linear dimension 19 m and mass 1200 tonne, with a precision in the low mm range. Conceptual designs for these tools have been elaborated with the collaboration of the Korean Domestic Agency (KO DA). The structural analysis was performed as well using ANSYS code. © 2011 Elsevier B.V. All rights reserved.

Nam K.,ITER Korea | Park H.,ITER Korea | Im K.,ITER Korea | Kim D.,ITER Korea | And 5 more authors.
Fusion Engineering and Design | Year: 2013

The purpose-built, ITER tokamak assembly tools, which are to be provided by Korea, should be designed to meet: the assembly plan, space reservations, safety standards, simple operations, efficient maintenance, and so on. It is very important that the ITER assembly tools are able to lift and transfer ITER components or their sub-assemblies to their assembled position safely. Furthermore, the lifting tools will lift and handle very heavy loads that can be more than 1200 tonnes sometimes. Therefore, the ITER lifting tools must be designed to endure these heavy load conditions with regard to their structural integrity. Also, these designs should be verified through an appropriate method. The preliminary design of the sector lifting tool and associated lifting attachments are introduced in this paper. The sector lifting tool was designed especially to lift and handle various ITER components by adjusting the lifting centre. The structural analysis results using ANSYS are described considering the heaviest load condition. The results of the analysis show that; all stresses applied on the lifting tool are lower than the allowable stress of the applied material. © 2013 Elsevier B.V. All rights reserved.

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