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Korea is supposed to develop the ITER tritium storage and delivery system (SDS), which is one of the main components of the ITER tritium plant. For successful procurement, there are several ongoing R&D activities in the detailed design phase. Investigation of design parameters of the storage and delivery beds has been performed. Small and large-scale mock-ups of ZrCo beds are used to test the...
For the design of the European procurement package for the ITER Water Detritiation System (WDS) an experimental WDS called TRENTA3 was installed and commissioned at the Tritium Laboratory Karlsruhe (TLK). For TRENTA3 a Combined Electrolysis and Catalytic Exchange (CECE) process has been applied. Two electrolyzer units with a total capacity of 2 (N)m3 h-1 H2 and a Liquid Phase Catalytic Exchange (LPCE)...
This paper presents an overview of the safety related operating feedback taken into account in the ITER baseline design, and of the previously completed and ongoing Research and Development (R&D) activities in support of ITER safety analyses. Operating feedback relevant to ITER mostly comes from previous and currently existing fusion devices, and from the operation of tritium laboratories. Regarding...
The tritium storage and delivery system (SDS) is one of the main components of the ITER tritium plant. There are several R&D activities on-going for the detailed design. The verification of design parameters of the SDS beds has been performed. Several types of ZrCo beds are under investigation to obtain desirable rapid delivery and recovery performance and to establish the pertinent procedure...
The mission of the proposed Fusion Development Facility (FDF) is to fill the gaps between ITER and current experiments and a fusion demonstration power plant (DEMO). FDF should carry forward Advanced Tokamak (AT) physics and enable development of fusion's energy applications. Near term advanced tokamak physics and non-superconducting magnet technology will be used to achieve steady-state with burn,...
A tritium assaying and dispensing system has been designed and is being constructed in KEPTL (Korea Electric Power Research Institute, Tritium Laboratory). This facility will be used to supply tritium from WTRF (Wolsong Tritium Removal Facility) to customers for industrial uses, R&D application, ITER operation and other purposes. In order to account the tritium amount loaded in and out this facility,...
Permeation is a complex phenomenon. Today the unique tool ITER QA pedigree qualified is a one dimensional tool, TMAP7, not suitable for the complex geometries present in the Breeding Blanket concepts, where 2D/3D simulation capacities of the permeation phenomenon are a real need. In pursuit of this objective, a group of new operators describing some of the different phenomena which make up the permeation...
A conceptual design has been developed for the recovery of un-expended fuel, ash, and associated post-detonation products from a ~ 2 GW IFE power reactor. The conceptual design incorporates systems for the safe, efficient collection, processing, and purification of IFE plasma exhaust fuel components. The system has been designed and sized such that tritium bred within blankets can also be collected,...
Tritium inventory and permeation are important data for a breeding blanket of a fusion reactor. For the HCPB TBM in ITER a first attempt has been done to calculate these data at the design stage using available analysis tools. The results are in the expected range but further validation work is needed
A pumping system designed to pump magnetic fusion reactors has been operated pumping deuterium, hydrogen and hydrogen-helium mixtures. A 500 mm bore liquid helium cooled "snail" cryocondensation pump was used to pump the hydrogen species. The snail pump is equipped with a unique regeneration head which continuously removes the hydrogen ice from the cryocondensation surfaces while the pump...
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