R&amp;D on support to ITER safety assessment

Dorsselaere, J.P. Van; Perrault, Didier; Barrachin, M.; Boutarfaïa, Ahmed; Bez, Jeremy; Cortes, Pierre; Séropian, C.; Trégourès, Nicolas; Vendel, J.

doi:10.1016/j.fusengdes.2008.11.091

Cited by 13 publications

(8 citation statements)

References 14 publications

(18 reference statements)

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“…For the design and licensing of the nuclear fusion power plant computational fluid dynamics (CFD), codes are considered an essential tool [83]. Accuracy is also required for the CFD analysis of a LOVA in order to provide essential data to the engineering and designers to design the safety features.…”

Section: Advances In Materials Science and Engineeringmentioning

confidence: 99%

Safety Analysis in Large Volume Vacuum Systems Like Tokamak: Experiments and Numerical Simulation to Analyze Vacuum Ruptures Consequences

Malizia

Lupelli

Richetta

et al. 2014

Advances in Materials Science and Engineering

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The large volume vacuum systems are used in many industrial operations and research laboratories. Accidents in these systems should have a relevant economical and safety impact. A loss of vacuum accident (LOVA) due to a failure of the main vacuum vessel can result in a fast pressurization of the vessel and consequent mobilization dispersion of hazardous internal material through the braches. It is clear that the influence of flow fields, consequence of accidents like LOVA, on dust resuspension is a key safety issue. In order to develop this analysis an experimental facility is been developed: STARDUST. This last facility has been used to improve the knowledge about LOVA to replicate a condition more similar to appropriate operative condition like to kamaks. By the experimental data the boundary conditions have been extrapolated to give the proper input for the 2D thermofluid-dynamics numerical simulations, developed by the commercial CFD numerical code. The benchmark of numerical simulation results with the experimental ones has been used to validate and tune the 2D thermofluid-dynamics numerical model that has been developed by the authors to replicate the LOVA conditions inside STARDUST. In present work, the facility, materials, numerical model, and relevant results will be presented.

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Section: Advances In Materials Science and Engineeringmentioning

confidence: 99%

Safety Analysis in Large Volume Vacuum Systems Like Tokamak: Experiments and Numerical Simulation to Analyze Vacuum Ruptures Consequences

Malizia

Lupelli

Richetta

et al. 2014

Advances in Materials Science and Engineering

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“…It has been long realised that dust remobilization is a major safety issue for ITER and future fusion devices, owing to the possibility of radioactive or toxic dust release upon loss of vacuum accidents (LOVAs) [1][2][3]. In such scenarios, air ingress in the vacuum vessel creates an outward flow after pressure equilibration which leads to hydrodynamic forces that can potentially mobilize dust grains [4,5].…”

Section: Introductionmentioning

confidence: 99%

“…Remobilization concerns the in-vessel release of dust residing away from its production site, whereas the general term mobilization also includes the release of dust upon creation (cracking, melt layer splashing, delamination, arcing). It has been long realised that dust remobilization is a major safety issue for ITER and future fusion devices, owing to the possibility of radioactive or toxic dust release upon loss of vacuum accidents (LOVAs) [1][2][3]. In such scenarios, air ingress in the vacuum vessel creates an outward flow after pressure equilibration which leads to hydrodynamic forces that can potentially mobilize dust grains [4,5].…”

Section: Introductionmentioning

confidence: 99%

Dust remobilization in fusion plasmas under steady state conditions

Tolias

Ratynskaia

Angeli

et al. 2016

Plasma Phys. Control. Fusion

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The first combined experimental and theoretical studies of dust remobilization by plasma forces are reported. The main theoretical aspects of remobilization in fusion devices under steady state conditions are analyzed. In particular, the dominant role of adhesive forces is highlighted and generic remobilization conditions -direct lift-up, sliding, rolling -are formulated. A novel experimental technique is proposed, based on controlled adhesion of dust grains on tungsten samples combined with detailed mapping of the dust deposition profile prior and post plasma exposure. Proof-ofprinciple experiments in the TEXTOR tokamak and the EXTRAP-T2R reversed-field pinch are presented. The versatile environment of the linear device Pilot-PSI allowed for experiments with different magnetic field topologies and varying plasma conditions that were complemented with camera observations.

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“…Since 2009 [2], a large effort has been undertaken to investigate the key items and extend the capabilities of the ASTEC code [3] to address the main accident sequences which may occur in the fusion installations, in particular in ITER, an experimental installation for which IRSN provides assistance to the French Nuclear Safety Authority (ASN) regarding nuclear safety and radiation protection. First analysis of accidental scenarios led to identify the gaps of knowledge and to focus the efforts to improve the modelling for some issues related on one hand to reference accidental situations that may lead to the loss of confinement and on the other hand to the evaluation of their consequences in terms of potential releases to the environment.…”

Section: Introductionmentioning

confidence: 99%