Journal Article10.13182/FST05-A939
ITER Dynamic Tritium Inventory Modeling Code
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TL;DR: A tool for tritium inventory evaluation within each sub-system of the Fuel Cycle of ITER is described in this paper. But this tool is not available for the entire ITER system.
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Abstract: A tool for tritium inventory evaluation within each sub-system of the Fuel Cycle of ITER is vital, with respect to both the process of licensing ITER and also for operation. It is very likely that ...
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Citations
The ITER tritium systems
Manfred Glugla,A. Antipenkov,S. Beloglazov,C. J. Caldwell-Nichols,Ion Cristescu,I.-R. Cristescu,Chr. Day,L. Doerr,J.-P. Girard,E. Tada +9 more
- 01 Oct 2007
TL;DR: ITER is the first fusion machine fully designed for operation with equimolar deuterium-tritium mixtures as mentioned in this paper, and it is equipped with a neutral beam heating system.
157
ITER fuel cycle R&D: consequences for the design
Manfred Glugla,D.K. Murdoch,A. Antipenkov,S. Beloglazov,Ion Cristescu,I.-R. Cristescu,C. Day,R. Laesser,A. Mack +8 more
TL;DR: The ITER fuel cycle is designed to handle considerable flow rates of tritium with high flexibility and reliability; experimental work is ongoing to validate these designs Cryo-pumping systems for torus exhaust and neutral beam injectors have been tested to confirm fast regeneration scenarios and to reduce the accumulation of semi-permanent inventories of tritiated impurities as mentioned in this paper.
100
Commissioning of water detritiation and cryogenic distillation systems at TLK in view of ITER design
Ion Cristescu,I. Cristescu,L. Dörr,Manfred Glugla,G. Hellriegel,R. Michling,D.K. Murdoch,P. Schäfer,Stefan Welte,W. Wurster +9 more
- 01 Oct 2007
TL;DR: In this paper, an experimental facility called TRENTA and representative of the ITER WDS and ISS protium separation column has been commissioned at Tritium Laboratory Karlsruhe (TLK), consisting of Combined Electrolysis Catalytic Exchange (CECE) process, with an LPCE column of 8m, in combination with a cryogenic distillation (CD) process.
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Dynamic optimization of cryogenic distillation operation for hydrogen isotope separation in fusion power plant
TL;DR: In this paper, the authors proposed a dynamic control policy to minimize the tritium inventory and satisfy the product quality specifications in a hydrogen isotope separation system, which is based on a rigorous dynamic model for packed columns to simulate realistic behaviors of cryogenic distillation.
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Tritium inventory assessment for ITER using TRIMO
TL;DR: In this paper, the authors proposed a fuel handling strategy during tritium inventory assessment in the main sub-systems of the ITER Fuel Cycle, based on the dynamic modelling code TRIMO.
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References
Plasma{material interactions in current tokamaks and their implications for next step fusion reactors
G. Federici,C. H. Skinner,Jeffrey N. Brooks,J. P. Coad,C. Grisolia,A.A. Haasz,Ahmed Hassanein,V. Philipps,C. S. Pitcher,J. Roth,W R Wampler,Dennis Whyte +11 more
TL;DR: In this article, the authors review the underlying physical processes and the existing experimental database of plasma-material interactions both in tokamaks and laboratory simulation facilities for conditions of direct relevance to next-step fusion reactors.
Plasma-material Interactions in Current Tokamaks and their Implications for Next-step Fusion Reactors
G. Federici,C.H. Skinner,Jeffrey N. Brooks,J.P. Coad,C. Grisolia +4 more
- 10 Jan 2001
TL;DR: In this article, the underlying physical processes and the existing experimental database of plasma-material interactions both in tokamaks and laboratory simulation facilities for conditions of direct relevance to next-step fusion reactors are reviewed.
Recovery of tritium from different sources by the ITER tokamak exhaust processing system
TL;DR: The TEP process is designed to be fully continuous and based on permeation of hydrogen isotopes through palladium/silver (first process step), heterogeneously catalyzed cracking or conversion reactions (second process step) and countercurrent isotopic swamping (third process step). The overall decontamination factor for tritium removal from tokamak exhaust gas at a composition as specified for the DT phase of ITER is at least 10 8.
29
CFTSIM-ITER dynamic fuel cycle model
A. Busigin,P. Gierszewski +1 more
TL;DR: CFTSIM as discussed by the authors is a dynamic fuel cycle model for the ITER tritium processing system, which can be used to understand and optimize the behavior of ITER fuel cycle, and also has an easier-to-use graphical interface.
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Steady State and Dynamic Simulation of the ITER Hydrogen Isotope Separation System
A. Busigin,S.K. Sood +1 more
TL;DR: In this article, the authors presented a steady state and dynamic simulation study of the ITER Hydrogen Isotope Separation System (ISS) under start-up conditions using the DYNSIM code.
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