16 results on '"Ciurluini, C."'
Search Results
2. A systematic approach for the adequacy analysis of a set of experimental databases: Application in the framework of the ATRIUM activity
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Baccou, J., Glantz, T., Ghione, A., Sargentini, L., Fillion, P., Damblin, G., Sueur, R., Iooss, B., Fang, J., Liu, J., Yang, C., Zheng, Y., Ui, A., Saito, M., Mendizábal Sanz, R., Bersano, A., Mascari, F., Skorek, T., Tiborcz, L., Hirose, Y., Takeda, T., Nakamura, H., Choi, C., Heo, J., Petruzzi, A., Zeng, K., Xie, Z., Wu, X., Eguchi, H., Pangukir, F., Breijder, P., Franssen, S., Perret, G., Clifford, I.D., Coscia, T.M., Di Maio, F., Zio, E., Pedroni, N., Zhang, J., Freixa, J., Rizzo, F., Ciurluini, C., Giannetti, F., and Adorni, M.
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- 2024
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3. Subchannel modelling capabilities of RELAP5-3D© for wire-spaced fuel pin bundle
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Ciurluini, C., Narcisi, V., Giannetti, F., Lorusso, P., Tarantino, M., and Caruso, G.
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- 2023
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4. Thermal-hydraulic assessment of Once-Through Steam Generators for EU-DEMO WCLL Breeding Blanket primary cooling system application
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Ciurluini, C., Vannoni, Alessandra, Del Moro, Tommaso, Lorusso, Pierdomenico, Tincani, Amelia, Del Nevo, Alessandro, Barucca, Luciana, and Giannetti, Fabio
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- 2023
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5. Transient analysis of a locked rotor/shaft seizure accident involving the EU-DEMO WCLL Breeding Blanket primary cooling circuits
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Ciurluini, C., D'Onorio, M., Giannetti, F., Caruso, G., and Del Nevo, A.
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- 2023
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6. Maturation of critical technologies for the DEMO balance of plant systems
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Barucca, L., Hering, W., Perez Martin, S., Bubelis, E., Del Nevo, A., Di Prinzio, M., Caramello, M., D'Alessandro, A., Tarallo, A, Vallone, E., Moscato, I., Quartararo, A., D'amico, S, Giannetti, F., Lorusso, P., Narcisi, V., Ciurluini, C., Montes Pita, M.J., Sánchez, C., Rovira, A., Santana, D., Gonzales, P., Barbero, R., Zaupa, M., Szogradi, M., Normann, S., Vaananen, M., Ylatalo, J., Lewandowska, M., Malinowski, L., Martelli, E., Froio, A., Arena, P., and Tincani, A.
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- 2022
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7. Tokamak cooling systems and power conversion system options
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Moscato, I., Barucca, L., Bubelis, E., Caruso, G., Ciattaglia, S., Ciurluini, C., Del Nevo, A., Di Maio, P.A., Giannetti, F., Hering, W., Lorusso, P., Martelli, E., Narcisi, V., Norrman, S., Pinna, T., Perez-Martin, S., Quartararo, A., Szogradi, M., Tarallo, A., and Vallone, E.
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- 2022
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8. Preliminary MHD pressure drop analysis for the prototypical WCLL TBM with RELAP5/MOD3.3
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Melchiorri, L., Narcisi, V., Ciurluini, C., Giannetti, F., Caruso, G., and Tassone, A.
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- 2022
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9. Conceptual design overview of the ITER WCLL Water Cooling System and supporting thermal-hydraulic analysis
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Ciurluini, C., Narcisi, V., Tincani, A., Ferrer, C. Ortiz, and Giannetti, F.
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- 2021
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10. Conceptual design of the main Ancillary Systems of the ITER Water Cooled Lithium Lead Test Blanket System
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Ruggero Forte, Veronica Pierantoni, Rocco Mozzillo, Antonio Cammi, Emanuela Martelli, Claudio Tripodo, I. Catanzaro, Pietro Alessandro Di Maio, Vincenzo Narcisi, Carlos Alfonso Reyes Ortiz, Andrea Tarallo, Balazs Lesko, Fabio Giannetti, Jessica Korzeniowska, Marco Utili, Erik Walcz, Stefano Lorenzi, Gandolfo Alessandro Spagnuolo, Maurizio Bruzzone, I. Ricapito, Pierluigi Chiovaro, Ferruccio Paoletti, A. Tincani, Cristiano Ciurluini, Konstantina Voukelatou, P. Arena, Alessandro Del Nevo, Carlos Hugo Moreno, Tincani A., Arena P., Bruzzone M., Catanzaro I., Ciurluini C., Del Nevo A., Di Maio P.A., Forte R., Giannetti F., Lorenzi S., Martelli E., Moreno C., Mozzillo R., Ortiz C., Paoletti F., Pierantoni V., Ricapito I., Spagnuolo G.A., Tarallo A., Tripodo C., Cammi A., Utili M., Voukelatou K., Walcz E., Lesko B., Korzeniowska J., Chiovaro P., Narcisi V., Tincani, A., Arena, P., Bruzzone, M., Catanzaro, I., Ciurluini, C., Del Nevo, A., Di Maio, P. A., Forte, R., Giannetti, F., Lorenzi, S., Martelli, E., Moreno, C., Mozzillo, R., Ortiz, C., Paoletti, F., Pierantoni, V., Ricapito, I., Spagnuolo, G. A., Tarallo, A., Tripodo, C., Cammi, A., Utili, M., Voukelatou, K., Walcz, E., Lesko, B., Korzeniowska, J., Chiovaro, P., and Narcisi, V.
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Nuclear engineering ,CPS ,ITER ,PbLi loop ,TES ,WCLL TBS ,WCS ,chemistry.chemical_element ,Blanket ,01 natural sciences ,010305 fluids & plasmas ,Conceptual design ,0103 physical sciences ,Water cooling ,General Materials Science ,010306 general physics ,Settore ING-IND/19 - Impianti Nucleari ,Civil and Structural Engineering ,Mechanical Engineering ,Water cooled ,Coolant ,Nuclear Energy and Engineering ,chemistry ,Environmental science ,Systems design ,Lithium - Abstract
The Water Cooled Lithium Lead Test Blanket System (WCLL TBS) is one of the EU Test Blanket Systems candidate for being installed and operated in ITER. In view of its Conceptual Design Review by F4E and ITER Organization (IO), planned for mid-September 2020, several technical activities have been performed in the areas of WCLL TBS Ancillary Systems design. In this article the outcomes of the conceptual design phase of the four main Ancillary Systems of WCLL TBS, namely the Water Cooling System (WCS), the Coolant Purification System (CPS), the PbLi loop and the Tritium Extraction System (TES), are reported and critically discussed. In particular, for each Ancillary System hereafter are reported: i) a short design description, including the conceptual design of their main components together with their operative conditions under the so-called Normal Operational State (NOS), ii) the ESP-ESPN classification for their main components, and iii) their arrangement and integration in the assigned ITER areas (PC#16, Vertical Shaft, TCWS Vault, Galleries and Tritium Process Room).
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- 2021
11. Maturation of critical technologies for the DEMO balance of plant systems
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L. Barucca, W. Hering, S. Perez Martin, E. Bubelis, A. Del Nevo, M. Di Prinzio, M. Caramello, A. D'Alessandro, A Tarallo, E. Vallone, I. Moscato, A. Quartararo, S D'amico, F. Giannetti, P. Lorusso, V. Narcisi, C. Ciurluini, M.J. Montes Pita, C. Sánchez, A. Rovira, D. Santana, P. Gonzales, R. Barbero, M. Zaupa, M. Szogradi, S. Normann, M. Vaananen, J. Ylatalo, M. Lewandowska, L. Malinowski, E. Martelli, A. Froio, P. Arena, A. Tincani, Barucca, L., Hering, W., Perez Martin, S., Bubelis, E., Del Nevo, A., Di Prinzio, M., Caramello, M., D'Alessandro, A., Tarallo, A, Vallone, E., Moscato, I., Quartararo, A., D'amico, S, Giannetti, F., Lorusso, P., Narcisi, V., Ciurluini, C., Montes Pita, M.J., Sánchez, C., Rovira, A., Santana, D., Gonzales, P., Barbero, R., Zaupa, M., Szogradi, M., Normann, S., Vaananen, M., Ylatalo, J., Lewandowska, M., Malinowski, L., Martelli, E., Froio, A., Arena, P., and Tincani, A.
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Technology ,Balance of plant ,Electric power distribution ,Mechanical Engineering ,HCPB BB ,Steam generator ,Power conversion system ,Power plants -- Design and construction ,Nuclear Energy and Engineering ,Steam-boilers ,General Materials Science ,Power-plants -- Europe ,balance of plant ,DEMO ,power conversion system ,steam generator ,WCLL BB ,ddc:600 ,Settore ING-IND/19 - Impianti Nucleari ,Civil and Structural Engineering - Abstract
The Pre-Concept Design (PCD) of the Balance of Plant (BoP) systems of the EU-DEMO power plant is described in this paper for both breeding blanket (BB) concepts under assessment, namely the Water Cooled Lithium Lead (WCLL) BB and the Helium Cooled Pebble Bed (HCPB) BB. Moreover, the results of a preliminary evaluation of a number of BoP variants are discussed. This paper outlines the steps of the BoP design development, highlighting the project objectives and the strategy for their achievement under the very challenging requirements which include, among others, the intermittent nature of the DEMO plasma heat source. The main achievements during the PCD Phase will be reported together with the development plan for the Concept Design (CD) Phase to reach a mature (feasible) BoP concept for DEMO., peer-reviewed
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- 2022
12. Tokamak cooling systems and power conversion system options
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I. Moscato, L. Barucca, E. Bubelis, G. Caruso, S. Ciattaglia, C. Ciurluini, A. Del Nevo, P.A. Di Maio, F. Giannetti, W. Hering, P. Lorusso, E. Martelli, V. Narcisi, S. Norrman, T. Pinna, S. Perez-Martin, A. Quartararo, M. Szogradi, A. Tarallo, E. Vallone, Moscato I., Barucca L., Bubelis E., Caruso G., Ciattaglia S., Ciurluini C., Del Nevo A., Di Maio P.A., Giannetti F., Hering W., Lorusso P., Martelli E., Narcisi V., Norrman S., Pinna T., Perez-Martin S., Quartararo A., Szogradi M., Tarallo A., and Vallone E.
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Balance of plant ,Nuclear Energy and Engineering ,DEMO ,PHTS ,balance of plant ,HCPB ,WCLL ,Mechanical Engineering ,General Materials Science ,Settore ING-IND/19 - Impianti Nucleari ,Civil and Structural Engineering - Abstract
DEMO will be a fusion power plant demonstrating the integration into the grid architecture of an electric utility grid. The design of the power conversion chain is of particular importance, as it must adequately account for the specifics of nuclear fusion on the generation side and ensure compatibility with the electric utility grid at all times. One of the special challenges the foreseen pulsed operation, which affects the operation of the entire heat transport chain. This requires a time-dependant analysis of different concept design approaches to ensure proof of reliable operation and efficiency to obtain nuclear licensing. Several architectures of Balance of Plant were conceived and developed during the DEMO Pre-Concept Design Phase in order to suit needs and constraints of the in-vessel systems, with particular regard to the different blanket concepts. At this early design stage, emphasis was given to the achievement of robust solutions for all essential Balance of Plant systems, which have chiefly to ensure feasible and flexible operation modes during the main DEMO operating phases – Pulse, Dwell and ramp-up/down – and to adsorb and compensate for potential fusion power fluctuations during plasma flat-top. Although some criticalities, requiring further design improvements were identified, these preliminary assessments showed that the investigated cooling system architectures have the capability to restore nominal conditions after any of the abovementioned cases and that the overall availability could meet the DEMO top-level requirements. This paper describes the results of the studies on the tokamak coolant and Power Conversion System (PCS) options and critically highlights the aspects that require further work.
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- 2022
13. Thermal-hydraulic modeling and analyses of the water-cooled EU DEMO using RELAP5 system code
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Gianfranco Caruso, Cristiano Ciurluini, Emanuela Martelli, Fabio Giannetti, Alessandro Del Nevo, Martelli, E., Giannetti, F., Ciurluini, C., Caruso, G., and Del Nevo, A.
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Nuclear engineering ,Thermal power station ,EU DEMO ,PHTS ,WCLL ,RELAP5 ,BoP ,Blanket ,01 natural sciences ,7. Clean energy ,Turbine ,Energy storage ,010305 fluids & plasmas ,Thermal hydraulics ,Conceptual design ,0103 physical sciences ,Heat exchanger ,General Materials Science ,010306 general physics ,Civil and Structural Engineering ,Mechanical Engineering ,Nuclear Energy and Engineering ,Heat transfer ,Nuclear fusion ,Environmental science - Abstract
The conceptual design of the Primary Heat Transfer System (PHTS) of the water-cooled European (EU) DEMO foresees two independent cooling circuits, the breeding zone PHTS and the first wall PHTS. During the pulse time (120 min) the first delivers thermal power to the turbine, the latter delivers thermal power to the Intermediate Heat Transfer System (IHTS) equipped by an Energy Storage System (ESS). The IHTS delivers partially thermal power to the turbine in pulse so that to accumulate a suitable amount of energy in ESS to operate the turbine during the dwell time (10 min) at almost constant load, despite the EU DEMO pulsation of the generated thermal power. A dynamic model of the primary systems of water-cooled EU DEMO is developed using RELAP5/Mod3.3 system code to verify components sizing and to investigate code predictive capabilities. The model includes the primary and secondary side of the breeding zone and first wall, and in particular: in-vessel (i.e. breeding blanket) and ex-vessel components (i.e. main collectors, hot and cold legs, heat exchangers, steam generators, pumps). Preliminary assessments of the nodalization have been carried out, in particular checking pressure drops along the systems and heat exchanger performances.
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- 2019
14. Analysis of the thermal-hydraulic behavior of the EU-DEMO WCLL breeding blanket cooling systems during a loss of flow accident
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Gianfranco Caruso, Cristiano Ciurluini, L. Barucca, Emanuela Martelli, Alessandro Del Nevo, Fabio Giannetti, Ciurluini, C., Giannetti, F., Martelli, E., Del Nevo, A., Barucca, L., and Caruso, G.
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Balance of plant ,RELAP5 ,Mechanical Engineering ,Nuclear engineering ,balance of plant ,DEMO ,loss of flow accident ,primary heat transfer system ,Blanket ,7. Clean energy ,01 natural sciences ,Turbine ,Primary heat transfer system ,010305 fluids & plasmas ,Coolant ,Thermal hydraulics ,Dwell time ,Breeder (animal) ,Nuclear Energy and Engineering ,0103 physical sciences ,Heat transfer ,Heat exchanger ,Environmental science ,General Materials Science ,Loss of flow accident ,010306 general physics ,Civil and Structural Engineering - Abstract
The water-cooled EU-DEMO Breeding Blanket (BB) is cooled by two independent circuits, the Breeder Zone (BZ) and the First Wall (FW) Primary Heat Transfer Systems (PHTS). The configuration under study foresees the presence of an Intermediate Heat Transfer System and an Energy Storage System to operate the turbine during both the pulse (2 h) and the dwell time (10 min) at almost constant load, despite the plasma power pulsation. Within the framework of the EUROfusion WPBOP research activity, a RELAP5/Mod3.3 model was developed to investigate the thermal-hydraulic behavior of the primary cooling systems during transient conditions belonging to the category of “Decrease in Coolant System Flow Rate”. The nodalization includes the BB, the PHTS circuits, the BZ Once Through Steam Generators and the FW Heat EXchangers. The model was initially used to simulate the nominal conditions with the pulse and dwell phases. Then, starting from the pulse, a Loss of Flow Accident (LOFA) was selected to preliminary evaluate the PHTS behavior with the aim of the design improvement. LOFA analyses were performed considering the complete loss of both the FW and BZ PHTS main coolant pumps (MCPs). A sensitivity was carried out to assess the impact of the MCPs flywheel on the main PHTS parameters. Transient results highlighted the appropriateness of the current design with no need for further mitigation actions.
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- 2021
15. Thermal-hydraulic modeling and analysis of the Water Cooling System for the ITER Test Blanket Module
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Gianfranco Caruso, Alessandro Del Nevo, Cristiano Ciurluini, Fabio Cismondi, I. Ricapito, Fabio Giannetti, A. Tincani, Ciurluini, C., Giannetti, F., Tincani, A., Del Nevo, A., Caruso, G., Ricapito, I., and Cismondi, F.
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Nuclear engineering ,Heat sink ,Blanket ,01 natural sciences ,7. Clean energy ,010305 fluids & plasmas ,Thermal hydraulics ,TBM ,ITER ,0103 physical sciences ,Water cooling ,General Materials Science ,Sensitivity (control systems) ,010306 general physics ,Civil and Structural Engineering ,RELAP5 ,Mechanical Engineering ,NOS ,WCLL ,Nuclear Energy and Engineering ,Duty cycle ,Heat transfer ,Environmental science ,WCS ,Transient (oscillation) - Abstract
The Water Cooled Lithium Lead (WCLL) is one of the selected breeding blanket (BB) concepts to be investigated in the EUROfusion Breeding Blanket Project (WPBB), and it was also recently chosen as one of the mock-up for ITER Test Blanket Module (TBM) program. The program foresees the test of different BB mock-ups, called Test Blanket Modules, with all the related ancillary systems. A pre-conceptual design of the Water Cooling System (WCS) of the ITER WCLL-TBM was developed considering the same cooling function of the EU-DEMO WCLL-BB primary heat transfer system (PHTS), but matching different boundary conditions: a scaled source power and far lower heat sink temperatures. A complete thermal-hydraulic (TH) model of the WCS loop and TBM set was developed using a modified version of RELAP5/Mod3.3 system code to verify component sizing and to investigate the system behavior during steady-state and transient conditions. The full plasma power scenario was simulated and used as an initial condition for transient calculations. ITER Normal Operational State (NOS) was studied to evaluate the system response. Simulation results highlighted the need for an electric heater to keep the WCS system in stable operation. A sensitivity analysis was carried out to optimize the heater duty cycle.
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16. Conceptual design overview of the ITER WCLL Water Cooling System and supporting thermal-hydraulic analysis
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Vincenzo Narcisi, Fabio Giannetti, A. Tincani, C. Ortiz Ferrer, Cristiano Ciurluini, Ciurluini, C., Narcisi, V., Tincani, A., Ferrer, C. O., and Giannetti, F.
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Nuclear engineering ,02 engineering and technology ,Heat sink ,7. Clean energy ,01 natural sciences ,010305 fluids & plasmas ,Thermal hydraulics ,TBM ,0203 mechanical engineering ,Conceptual design ,Economizer ,ITER ,0103 physical sciences ,Heat exchanger ,Water cooling ,General Materials Science ,Civil and Structural Engineering ,Temperature control ,LOHS ,RELAP5 ,Mechanical Engineering ,WCS ,Coolant ,020303 mechanical engineering & transports ,Nuclear Energy and Engineering ,Environmental science - Abstract
In this paper, the conceptual design of the International Thermonuclear Experimental Reactor (ITER) Water-Cooled Lithium-Lead (WCLL) Test Blanket Module (TBM) Water Cooling System (WCS) from Europe is presented. The system consists of two loops in series. This design feature allows the removal of heat from the TBM box avoiding at the same time the release of radionuclides into the ITER Component Cooling Water System (CCWS), that acts as WCLL Test Blanket System heat sink. For this purpose, the WCS primary loop deals with the direct heat removal from the ITER TBM and the secondary one implements physical separation between the contaminated primary loop coolant and the CCWS. The insertion of an economizer into the primary loop determines the characteristic “eight” shape of the circuit. This choice was done in order to reduce the temperature difference on the intermediate heat exchanger. Hairpin type and steam bubble are the technologies selected for heat exchangers and pressurizers, respectively. Pressure and temperature control systems are foreseen to limit excursions from rated values in normal operational states and abnormal transients. A computational activity was promoted to assess the WCLL-WCS conceptual design, using a modified version of the RELAP5 Mod3.3 system code. A detailed thermal-hydraulic model was developed on the basis of design outcomes. The nodalization scheme includes the TBM, the WCS, a portion of the CCWS and the lithium-lead circuit. The computational campaign involved both the normal operational state and selected abnormal transients. In all the scenarios simulated, the conceptual design has highlighted the capability of operating the system respecting all the thermal-hydraulic requirements. The abnormal transient selected and presented is the loss of flow in the CCWS (loss of heat sink). In these conditions, TBM cooling function has been verified, keeping standard control strategies without any external action.
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