DEMO Divertor Cassette and Plasma facing Unit in Vessel Loss-of-Coolant Accident

Dongiovanni, Danilo Nicola; D’Onorio, Matteo; Caruso, Gianfranco; Pinna, T.; Porfiri, M.T.

doi:10.3390/en15238879

Cited by 4 publications

(4 citation statements)

References 23 publications

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“…Consequently, a large amount of coolant could be released in the containment after a LOCA event. Preliminary analyses in [16][17][18] highlighted that ex-vessel LOCA from water PHTS could pose a safety concern because of the high enthalpy released in the building. For this reason, mitigation systems (e.g., suppression pools, containment spray system) shall be foreseen in the containment to avoid long-term releases of tritiated water (HTO) and activated corrosion products (ACP) toward the environment.…”

Section: Introductionmentioning

confidence: 99%

Development of a Thermal-Hydraulic Model for the EU-DEMO Tokamak Building and LOCA Simulation

et al. 2023

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The EU-DEMO must demonstrate the possibility of generating electricity through nuclear fusion reactions. Moreover, it must denote the necessary technologies to control a powerful plasma with adequate availability and to meet the safety requirements for plant licensing. However, the extensive radioactive materials inventory, the complexity of the plant, and the presence of massive energy sources require a rigorous safety approach to fully realize fusion power’s environmental advantages. The Tokamak building barrier design must address two main issues: radioactive mass transport hazards and energy-related or pressure/vacuum hazards. Safety studies are performed in the frame of the EUROfusion Safety And Environment (SAE) work package to support design improvement and evaluate the thermal-hydraulic behavior of confinement building environments during accident conditions in addition to source term mobilization. This paper focuses on developing a thermal-hydraulic model of the EU-DEMO Tokamak building. A preliminary model of the heat ventilation and air conditioning system and vent detritiation system is developed. A loss-of-coolant accident is studied by investigating the Tokamak building pressurization, source term mobilization, and release. Different nodalizations were compared, highlighting their effects on source term estimation. Results suggest that the building design should be improved to maintain the pressure below safety limits; some mitigative systems are preliminarily investigated for this purpose.

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Section: Introductionmentioning

confidence: 99%

Development of a Thermal-Hydraulic Model for the EU-DEMO Tokamak Building and LOCA Simulation

et al. 2023

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“…When considering the radioactive contamination of a cooling system of a nuclear plant, the ACPs study is helpful for the optimization of plant operation and, at the same time, the reduction of occupational radiation exposure when the source term is considered. Moreover, the source term, including ACP, can be mobilized during accident scenarios [2,3].…”

Section: Introductionmentioning

confidence: 99%

Water Chemistry Impact on Activated Corrosion Products Assessment in Tokamak Reactors

Molinari¹,

D’Onorio²,

Mariano³

et al. 2023

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Activated Corrosion Products (ACPs) formation and deposition pose a critical safety issue for nuclear fusion reactors. The working fluid transports the ACPs towards regions accessible to worker personnel. Predicting ACPs formation deposition and transport is fundamental for source term identification, reduction of radiation exposure assessment, maintenance plan definition, design optimization, and waste management. The code OSCAR-Fusion has been developed by the CEA (France) to evaluate the ACPs generation and transport in closed water-cooled loops for fusion application. This work aims at assessing the impact of water chemistry on the transport, precipitation, and deposition of corrosion products for the EU-DEMO divertor Plasma Facing Unit Primary Heat Transfer System. Sensitivity analyses and uncertainty quantification are needed due to the multi-physics phenomena involved in ACPs formation and transport. The OSCAR-Fusion/RAVEN code coupling developed by the Sapienza University of Rome and ENEA has been used. This work presents the perturbation results of different parameters chosen for a closed water-cooled loop considering a continuous scenario of 1888 days. The aim of this work is to assess the variation of build-up of ACPs, perturbing the alkalizing agent concentration into the coolant and the corrosion and release rates of different materials.

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“…When considering the radioactive contamination of a cooling system of a nuclear plant, the study of ACPs is helpful for the optimization of plant operation, avoiding the damage of the piping materials, as shown in [2] and, at the same time, the reduction of occupational radiation exposure when the source term is considered, as shown in [3]. Moreover, the source term, including ACP, can be mobilized during accident scenarios [4,5].…”

Section: Introductionmentioning

confidence: 99%

“…The parametric study is performed considering the EU-DEMO Divertor Plasma Facing Unit PHTS, which verifies the code coupling [10]. The EU-DEMO Divertor has been previously studied to evaluate the mass and activity inventories, as described in [4,13,14].…”

Section: Introductionmentioning

confidence: 99%

Water Chemistry Impact on Activated Corrosion Products: An Assessment on Tokamak Reactors

et al. 2023

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Activated Corrosion Product (ACP) formation and deposition pose a critical safety issue for nuclear fusion reactors. The working fluid transports the ACPs towards regions accessible by worker personnel, i.e., the steam generator. The code OSCAR-Fusion has been developed by the CEA (France) to evaluate the ACP generation and transport in closed water-cooled loops for fusion application. This work preliminary assesses the impact of water chemistry on the transport, precipitation, and deposition of corrosion products for the EU-DEMO divertor Plasma Facing Unit Primary Heat Transfer System. Sensitivity analyses and uncertainty quantification are needed due to the multi-physics phenomena involved in ACP formation and transport. The OSCAR-Fusion/RAVEN code coupling developed by the Sapienza University of Rome and ENEA are used. This work presents the perturbation results of different parameters chosen for a closed water-cooled loop considering a continuous scenario of 1888 days. The aim of this work is to preliminarily assess the variation of build-up of ACPs, perturbing the alkalizing agent concentration into the coolant, and the corrosion and release rates of different materials. The assessment of ACP formation deposition and transport is fundamental for source term identification, reduction of radiation exposure assessment, maintenance plan definition, design optimization, and waste management.

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DEMO Divertor Cassette and Plasma facing Unit in Vessel Loss-of-Coolant Accident

Cited by 4 publications

References 23 publications

Development of a Thermal-Hydraulic Model for the EU-DEMO Tokamak Building and LOCA Simulation

Development of a Thermal-Hydraulic Model for the EU-DEMO Tokamak Building and LOCA Simulation

Water Chemistry Impact on Activated Corrosion Products Assessment in Tokamak Reactors

Water Chemistry Impact on Activated Corrosion Products: An Assessment on Tokamak Reactors

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