ITER Dynamic Tritium Inventory Modeling Code

Cristescu, I.; Dörr, L.; Busigin, A.; Murdoch, D.

doi:10.13182/fst05-a939

Cited by 18 publications

(6 citation statements)

References 7 publications

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“…Unlike previous approaches to tritium transport modelling and fuel cycle design tools [9][10][11] , Aspen HYSYS will offer a user-friendly graphical interface that allows a quick modelling experience. It has also been largely validated over the years and its thousands of users due to its highly extended use in industry, as well as in academia, for performing steady state and dynamic simulations in process design and analysis 12 .…”

Section: Aspen Hysys and Isotopic Databasesmentioning

confidence: 99%

Advanced Tools for ITER Tritium Plant System Modeling and Design

Nougués¹,

Feliu²,

Campanyà³

et al. 2020

Fusion Science and Technology

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Chemical plants system modelling experience based on the use of largely validated commercial modelling tools such as Aspen HYSYS is adapted and exploited to develop numeric routines for unitary isotopic operations: permeation, cold trapping, reversible absorption and cryogenic distillation at ITER Tritium Plant Systems.Model prediction capabilities and isotopic database inputs for first principle models are discussed. Numeric implementation of Aspen HYSYS routines are presented.

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Section: Aspen Hysys and Isotopic Databasesmentioning

confidence: 99%

Advanced Tools for ITER Tritium Plant System Modeling and Design

Nougués¹,

Feliu²,

Campanyà³

et al. 2020

Fusion Science and Technology

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“…I.R. Cristescu (Germany) made a presentation of the dynamic mathematical model (TRIMO) for the fuel cycle of ITER [16]. Such a tool is valuable for tritium inventory evaluation within each system of the ITER fuel cycle in various operational scenarios.…”

Section: Tritium Safety and Inventoriesmentioning

confidence: 99%

Summary of the 8th IAEA Technical Meeting on Fusion Power Plant Safety

Girard

Gulden²,

Kolbasov

et al. 2008

Nucl. Fusion

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Reports were presented covering a selection of topics on the safety of fusion power plants. These included a review on licensing studies developed for ITER site preparation surveying common and non-common issues (i.e. site dependent) as lessons to a broader approach for fusion power plant safety. Several fusion power plant models, spanning from accessible technology to more advanced-materials based concepts, were discussed. On the topic related to fusion-specific technology, safety studies were reported on different concepts of breeding blanket modules, tritium handling and auxiliary systems under normal and accident scenarios' operation. The testing of power plant relevant technology in ITER was also assessed in terms of normal operation and accident scenarios, and occupational doses and radioactive releases under these testings have been determined. Other specific safety issues for fusion have also been discussed such as availability and reliability of fusion power plants, dust and tritium inventories and component failure databases. This study reveals that the environmental impact of fusion power plants can be minimized through a proper selection of low activation materials and using recycling technology helping to reduce waste volume and potentially open the route for its reutilization for the nuclear sector or even its clearance into the commercial circuit. Computational codes for fusion safety have been presented in support of the many studies reported. The on-going work on establishing validation approaches aiming at improving the prediction capability of fusion codes has been supported by experimental results and new directions for development have been identified. Fusion standards are not available and fission experience is mostly used as the framework basis for licensing and target design for safe operation and occupational and environmental constraints. It has been argued that fusion can benefit if a specific fusion approach is implemented, in particular for materials selection which will have a large impact on waste disposal and recycling and in the real limits of radiation releases if indexed to the real impact on individuals and the environment given the differences in the types of radiation emitted by tritium when compared with the fission products. Round table sessions resulted in some common recommendations. The discussions also created the awareness of the need for a larger involvement of the IAEA in support of fusion safety standards development.

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“…A dynamic model (TRIMO) of the tritium content in each sub-system of the fuel cycle of ITER was developed [2]. The code operates by solving the mass balance around each sub-system, progressing in each time step through fuelling, S459 torus, vacuum pumping, TEP, WDS, ISS and finally SDS.…”

Section: Tritium Needed For Operation and Inventories In The Fuel Cyc...mentioning

confidence: 99%

Tritium inventories and tritium safety design principles for the fuel cycle of ITER

et al. 2007

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Within the Tritium Plant of ITER a total inventory of about 2 to 3 kg will be necessary to operate the machine in the DT phase at a throughput of about 1 kg tritium per hour. During plasma operation, tritium will be distributed in the different subsystems of the fuel cycle. A tool for tritium inventory evaluation the dynamic model (TRIMO) of the tritium content in each subsystem of the Fuel Cycle of ITER was developed. The code reflects the design of each system; both the physical processes characteristics of each system and the associated control systems are modeled in TRIMO. The confinement of tritium within the respective systems of the Fuel Cycle is one of the most important safety objectives. The design of the deuterium / tritium fuel cycle of ITER includes a multiple barrier concept for the confinement of tritium and has two major features, namely a two (primary and secondary) barrier design and secondary containment atmosphere and gaseous waste treatment systems. Ultimately the building is equipped with a vent detritiation system and re-circulation type room atmosphere detritation systems, required as an emergency tritium confinement barrier during possible accidental events. In order to assure a high integrity of the tritium bearing systems within the ITER Tritium Plant the design considers largely protection measures (mainly overpressure and overtemperature protection).

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ITER Dynamic Tritium Inventory Modeling Code

Cited by 18 publications

References 7 publications

Advanced Tools for ITER Tritium Plant System Modeling and Design

Advanced Tools for ITER Tritium Plant System Modeling and Design

Summary of the 8th IAEA Technical Meeting on Fusion Power Plant Safety

Tritium inventories and tritium safety design principles for the fuel cycle of ITER

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