Thermal-hydraulic and thermo-mechanical simulations of Water-Heavy Liquid Metal interactions towards the DEMO WCLL breeding blanket design

Maio, P.A. Di; Arena, P.; D'Aleo, Fedele; Nevo, Alessandro Del; Eboli, Marica; Forte, Ruggero; Pesetti, Alessio

doi:10.1016/j.fusengdes.2019.04.093

Cited by 9 publications

(5 citation statements)

References 13 publications

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“…8 shows a comparison between the hoop strain at the strain gauges positions (see Fig. 3) extracted by the gauges data, the theory, the numerical simulations, and the results obtained in the previous work (Di Maio et al, 2019). We can see how, for most of the sensors, the numerical-experimental error lies lower than 10% with only SG-04 showing a higher value during tests A-1.4 and 2.3.…”

Section: Static Resultsmentioning

confidence: 62%

“…They provided extensive data on the thermodynamical interaction of water and Lead-Bismuth eutectic alloy (Del Nevo et al, 2019;Pesetti et al, 2016) with pressures ranging between 40 and 180 bars and temperatures of 400°C. Although this alloy is not utilized in fusion reactors, validation will be carried out also on these data for two main reasons: the results can be compared with previous modelling work (Di Maio et al, 2019) to gain confidence in their quality, and the validation can be performed on a wider database including different geometries. A second set of data comes from the LIFUS5/Mod3 facility (L5M3) which was instead operated using PbLi simulating LOCA events with pressures of around 180 bar and temperatures ranging between 300 and 400°C (Badodi et al, 2022;Eboli et al, 2019).…”

Section: Code Chain Validation: Methodology and Datamentioning

confidence: 99%

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SIMMER-III/ANSYS coupling (Preliminary development and validation activities of an integral tool for the design and analysis of WCLL components)

BADODI,

EBOLI,

CAMMI

et al. 2024

Mechanical Engineering Journal

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In the framework of the development of fusion energy, one of the most prominent technologies arising to address the issues of tritium breeding and power conversion is the Water-Cooled Lithium-Lead (WCLL). This technology utilizes a molten eutectic alloy of Lithium and Lead which circulates inside the Breeding Blanket (BB) and is irradiated with neutrons to produce tritium. Water is then circulated inside the system to cool the components. The simultaneous presence inside critical areas of the reactor of molten metal alloy and water, at high temperature and pressure, poses significant safety concerns. For this reason, adequate design and analysis techniques are required to ensure the ability of the system to survive and mitigate any possible damage in case of the in-box Loss of Coolant Accident (LOCA), the most critical postulated accidental scenario. With this aim in mind, a novel approach was implemented with the aim of coupling the SIMMER-III code and the ANSYS Mechanical code for the modelling of both the chemical and thermodynamical interactions between water and the alloy, and the resulting effects on the structures. This work presents the status of the coupling technique development and the results of the preliminary validation activities performed against experimental data provided by the LIFUS5 facility operating at ENEA Brasimone Research Centre. The resulting comparison between these data and the codes' predictions allows a careful evaluation of the errors introduced in each step of the chain. Moreover, it provides confidence in the capacity of the methodology to correctly predict the ability of the structures to withstand incidental loads without suffering extensive damage. This work aims at providing engineers with a usable and powerful tool that allows for the safety analysis of WCLL-based components during the early stages of the design phase. This would help save time, and effort and reduce the economic cost that might arise from any undetected issue propagating downstream the design process.

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Section: Static Resultsmentioning

confidence: 62%

Section: Code Chain Validation: Methodology and Datamentioning

confidence: 99%

SIMMER-III/ANSYS coupling (Preliminary development and validation activities of an integral tool for the design and analysis of WCLL components)

BADODI,

EBOLI,

CAMMI

et al. 2024

Mechanical Engineering Journal

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“…Finally, a chain of codes for the deterministic safety approach of the "in-box-LOCA" postulated accident will be set-up and applied. This will include coupling techniques [41], [42] and the use of thermo-mechanics codes [48]. These numerical tools will be used for supporting the design and the safety analyses of the WCLL TBM and BB.…”

Section: Future Activitiesmentioning

confidence: 99%

Fusion technologies development at ENEA Brasimone Research Centre: Status and perspectives

Tarantino

Martelli

Nevo

et al. 2020

Fusion Engineering and Design

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“…One of the configurations selected for DEMO purposes was the steam generator with bayonet tubes (SGBT) [4]. The SGBT concept stands out for its safety features, i.e., the reduced occurrence of water-Pb/Pb-alloy interaction [5][6][7], thanks to a double physical separation between the coolants and an easier monitoring of eventual leakages by pressurizing the separation region with inert gas.…”

Section: Introductionmentioning

confidence: 99%

Experimental Investigation on CIRCE-HERO for the EU DEMO PbLi/Water Heat Exchanger Development

et al. 2021

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The present paper describes the experimental campaign executed at the ENEA Brasimone Research Centre aiming at supporting the development of a PbLi/water heat exchanger suitable for the lithium–lead loops of the dual coolant lithium lead and the water cooled lithium lead breeding blankets of the EU DEMO fusion reactor. The experiments were performed in a test section named HERO, installed inside the main vessel of the lead–bismuth eutectic-cooled pool-type facility CIRCE. The test section hosts a steam generator bayonet tube mock-up in relevant scale, which was selected as a promising configuration for DEMO purposes. For the thermal-hydraulic characterization of the component, five tests were executed at different water pressures (6, 8, 12 MPa, two tests at 10 MPa), and liquid metal flow rates (40, 33, 27, 20, 10 kg/s). The experimental outcomes proved the technological feasibility of this novel steam generator and its suitability for the DEMO PbLi loops. The activity was completed with a post-test analysis using two versions of the system code RELAP5. Because the experiments were executed with lead–bismuth eutectic, a scaling analysis is proposed to find the equivalence with PbLi. RELAP5 code was applied to recalculate the experimental data using PbLi as working fluid.

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Thermal-hydraulic and thermo-mechanical simulations of Water-Heavy Liquid Metal interactions towards the DEMO WCLL breeding blanket design

Cited by 9 publications

References 13 publications

SIMMER-III/ANSYS coupling (Preliminary development and validation activities of an integral tool for the design and analysis of WCLL components)

SIMMER-III/ANSYS coupling (Preliminary development and validation activities of an integral tool for the design and analysis of WCLL components)

Fusion technologies development at ENEA Brasimone Research Centre: Status and perspectives

Experimental Investigation on CIRCE-HERO for the EU DEMO PbLi/Water Heat Exchanger Development

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