Claudio Nardi - Academia.edu (original) (raw)
Papers by Claudio Nardi
Convegno IGF XVI Catania 2002, 2008
Fusion Engineering and Design, 1998
Fusion Engineering and Design, Sep 1, 1998
The reference concept of the EU water-cooled Pb-17Li DEMO blanket is essentially formed by a dire... more The reference concept of the EU water-cooled Pb-17Li DEMO blanket is essentially formed by a directly-cooled steel box having the function of Pb-17Li container and by a double-wall U-tube bundle, immersed in the liquid metal, in which the pressurised water-coolant flows. The structural material is martensitic steel. All blanket performances satisfy DEMO requirements, such as tritium breeding self-sufficiency, capability of
Fusion Science and Technology
EU water-cooled Pb-17Li DEMO blanket: fabrication issues and future R&D priorities
The pre‐compression system is the keystone of ITER. A centripetal force of ∼30 MN will be applied... more The pre‐compression system is the keystone of ITER. A centripetal force of ∼30 MN will be applied at cryogenic conditions on top and bottom of each TF coil. It will prevent the ‘breathing effect’ caused by the bursting forces occurring during plasma operation that would affect the machine design life of 30000 cycles. Different alternatives have been studied throughout the years. There are two major design requirements limiting the engineering possibilities: 1) the limited available space and 2) the need to hamper eddy currents flowing in the structures. Six unidirectionally wound glass‐fibre composite rings (∼5 m diameter and ∼300 mm cross section) are the final design choice. The rings will withstand the maximum hoop stresses <500 MPa at room temperature conditions. Although retightening or replacing the pre‐compression rings in case of malfunctioning is possible, they have to sustain the load during the entire 20 years of machine operation. The present paper summarizes the pre‐...
Journal of Nuclear Materials, 1998
Fusion Engineering and Design, 1997
ABSTRACT The four blanket concepts developed within the European Fusion Technology program and su... more ABSTRACT The four blanket concepts developed within the European Fusion Technology program and supported by the European Community are assessed from the reliability/availability point of view. The reliability of blanket segments influences the availability of the whole plant. In case of a failure, the affected blanket segments must be repaired or exchanged. The mean down time necessary for segments repair or exchange is an important factor for the overall plant availability. It has been assumed to be 3 months for all concepts. To allow a meaningful comparative assessment, an identical evaluation scheme was applied to all concepts using the same basic data. The results show that differences in the availability of blanket concepts are relatively small, with availabilities ranging between 84.3 and 87.7%. The absolute numbers, however, are sensitive to assumptions and to failure modes taken into consideration.
Fusion Engineering and Design, 2001
ABSTRACT In the frame of the preliminary study of plants suitable for the energy production from ... more ABSTRACT In the frame of the preliminary study of plants suitable for the energy production from the fusion power, particular emphasis has been given on the divertor studies. Since a significant percentage of the power generated from the fusion process is absorbed in the divertor, the thermal efficiency of the power conversion cycle requires a high coolant outlet temperature of the divertor, leading to solutions that are different from those adopted for the present experimental fusion plants. Therefore, copper alloys having extremely high thermal conductivity, cannot be used as structural material for this kind of devices. The most suitable coolants to be used in the divertor are water, helium and liquid metals. A conceptual design study has been developed for each of these three fluids, with the aim to evaluate the maximum allowable thermal flux at the divertor target plate and the R&D requirements for each solution. While a water-cooled divertor can be designed with a limited R&D effort, the development of helium or liquid metal cooled divertors requires a more engaging R&D program.
Fusion Engineering and Design, 2005
This contribution presents the results of an experimental study on high temperature stress evolut... more This contribution presents the results of an experimental study on high temperature stress evolution in brazed Glidcop/W model structures. The investigated sample (23mm×23mm×8mm in volume) had been obtained by brazing a W alloy and a Glidcop (Cu alloy) platelet at 650°C using TiCuAg alloy as a filler. Neutron diffraction was utilized to determine the strains, then the stresses in the
Fusion Engineering and Design, 2010
Fusion Engineering and Design, 1999
This paper presents a short description of the latest design version of the water-cooled Pb–17Li ... more This paper presents a short description of the latest design version of the water-cooled Pb–17Li test-blanket module system and the proposal for the test program to be performed during the ITER Basic Performance Phase. The present R&amp;amp;amp;amp;amp;amp;amp;amp;amp;amp;amp;D program foresees to start the test on the first day of ITER operation. The test-blanket module is expected to use all technologies required
Fusion Engineering and Design, 2009
Fusion Engineering and Design, 2003
At the beginning of life ITER-FEAT will be equipped with a shielding blanket; nevertheless since ... more At the beginning of life ITER-FEAT will be equipped with a shielding blanket; nevertheless since many advantages can be envisaged in having a breeding blanket in the machine, such a concept has been investigated as well. It is a water-cooled blanket in which both ceramic breeder ...
Fusion Engineering and Design, 1998
Fusion Engineering and Design, 1998
The reference concept of the EU water-cooled Pb-17Li DEMO blanket is essentially formed by a dire... more The reference concept of the EU water-cooled Pb-17Li DEMO blanket is essentially formed by a directly-cooled steel box having the function of Pb-17Li container and by a double-wall U-tube bundle, immersed in the liquid metal, in which the pressurised water-coolant flows. The structural material is martensitic steel. All blanket performances satisfy DEMO requirements, such as tritium breeding self-sufficiency, capability of
Fusion Engineering and Design, 2005
Fusion Engineering and Design, 2008
Fusion Engineering and Design, 2005
Convegno IGF XVI Catania 2002, 2008
Fusion Engineering and Design, 1998
Fusion Engineering and Design, Sep 1, 1998
The reference concept of the EU water-cooled Pb-17Li DEMO blanket is essentially formed by a dire... more The reference concept of the EU water-cooled Pb-17Li DEMO blanket is essentially formed by a directly-cooled steel box having the function of Pb-17Li container and by a double-wall U-tube bundle, immersed in the liquid metal, in which the pressurised water-coolant flows. The structural material is martensitic steel. All blanket performances satisfy DEMO requirements, such as tritium breeding self-sufficiency, capability of
Fusion Science and Technology
EU water-cooled Pb-17Li DEMO blanket: fabrication issues and future R&D priorities
The pre‐compression system is the keystone of ITER. A centripetal force of ∼30 MN will be applied... more The pre‐compression system is the keystone of ITER. A centripetal force of ∼30 MN will be applied at cryogenic conditions on top and bottom of each TF coil. It will prevent the ‘breathing effect’ caused by the bursting forces occurring during plasma operation that would affect the machine design life of 30000 cycles. Different alternatives have been studied throughout the years. There are two major design requirements limiting the engineering possibilities: 1) the limited available space and 2) the need to hamper eddy currents flowing in the structures. Six unidirectionally wound glass‐fibre composite rings (∼5 m diameter and ∼300 mm cross section) are the final design choice. The rings will withstand the maximum hoop stresses <500 MPa at room temperature conditions. Although retightening or replacing the pre‐compression rings in case of malfunctioning is possible, they have to sustain the load during the entire 20 years of machine operation. The present paper summarizes the pre‐...
Journal of Nuclear Materials, 1998
Fusion Engineering and Design, 1997
ABSTRACT The four blanket concepts developed within the European Fusion Technology program and su... more ABSTRACT The four blanket concepts developed within the European Fusion Technology program and supported by the European Community are assessed from the reliability/availability point of view. The reliability of blanket segments influences the availability of the whole plant. In case of a failure, the affected blanket segments must be repaired or exchanged. The mean down time necessary for segments repair or exchange is an important factor for the overall plant availability. It has been assumed to be 3 months for all concepts. To allow a meaningful comparative assessment, an identical evaluation scheme was applied to all concepts using the same basic data. The results show that differences in the availability of blanket concepts are relatively small, with availabilities ranging between 84.3 and 87.7%. The absolute numbers, however, are sensitive to assumptions and to failure modes taken into consideration.
Fusion Engineering and Design, 2001
ABSTRACT In the frame of the preliminary study of plants suitable for the energy production from ... more ABSTRACT In the frame of the preliminary study of plants suitable for the energy production from the fusion power, particular emphasis has been given on the divertor studies. Since a significant percentage of the power generated from the fusion process is absorbed in the divertor, the thermal efficiency of the power conversion cycle requires a high coolant outlet temperature of the divertor, leading to solutions that are different from those adopted for the present experimental fusion plants. Therefore, copper alloys having extremely high thermal conductivity, cannot be used as structural material for this kind of devices. The most suitable coolants to be used in the divertor are water, helium and liquid metals. A conceptual design study has been developed for each of these three fluids, with the aim to evaluate the maximum allowable thermal flux at the divertor target plate and the R&D requirements for each solution. While a water-cooled divertor can be designed with a limited R&D effort, the development of helium or liquid metal cooled divertors requires a more engaging R&D program.
Fusion Engineering and Design, 2005
This contribution presents the results of an experimental study on high temperature stress evolut... more This contribution presents the results of an experimental study on high temperature stress evolution in brazed Glidcop/W model structures. The investigated sample (23mm×23mm×8mm in volume) had been obtained by brazing a W alloy and a Glidcop (Cu alloy) platelet at 650°C using TiCuAg alloy as a filler. Neutron diffraction was utilized to determine the strains, then the stresses in the
Fusion Engineering and Design, 2010
Fusion Engineering and Design, 1999
This paper presents a short description of the latest design version of the water-cooled Pb–17Li ... more This paper presents a short description of the latest design version of the water-cooled Pb–17Li test-blanket module system and the proposal for the test program to be performed during the ITER Basic Performance Phase. The present R&amp;amp;amp;amp;amp;amp;amp;amp;amp;amp;amp;D program foresees to start the test on the first day of ITER operation. The test-blanket module is expected to use all technologies required
Fusion Engineering and Design, 2009
Fusion Engineering and Design, 2003
At the beginning of life ITER-FEAT will be equipped with a shielding blanket; nevertheless since ... more At the beginning of life ITER-FEAT will be equipped with a shielding blanket; nevertheless since many advantages can be envisaged in having a breeding blanket in the machine, such a concept has been investigated as well. It is a water-cooled blanket in which both ceramic breeder ...
Fusion Engineering and Design, 1998
Fusion Engineering and Design, 1998
The reference concept of the EU water-cooled Pb-17Li DEMO blanket is essentially formed by a dire... more The reference concept of the EU water-cooled Pb-17Li DEMO blanket is essentially formed by a directly-cooled steel box having the function of Pb-17Li container and by a double-wall U-tube bundle, immersed in the liquid metal, in which the pressurised water-coolant flows. The structural material is martensitic steel. All blanket performances satisfy DEMO requirements, such as tritium breeding self-sufficiency, capability of
Fusion Engineering and Design, 2005
Fusion Engineering and Design, 2008
Fusion Engineering and Design, 2005
by Gregory Alegi, Virgilio Ilari, Immacolata Eramo, Balazs Juhasz, Emilio Gin, marco leofrigio, Teresa Silverio, Enrico Silverio, Mark D Mandeles, Giangiuseppe Pili, Stefano Rapisarda, Ferdinando Angeletti, Claudio Nardi, Maurizio Zinni, Riccardo Cappelli, Viviana Castelli, ENzo de Ianni, Gian Piero Siroli, and Raffaele Moncada
VVirgilio Ilari (Ed.). Contributors: Gregory Alegi, Mathias André, Ferdinando Angeletti, Christop... more VVirgilio Ilari (Ed.). Contributors: Gregory Alegi, Mathias André, Ferdinando Angeletti, Christopher Bassford, Jeremy Black, Mehdi Bouzoumita, Riccardo Cappelli, Viviana Castelli, Paolo Cau, Lucio Ceva, Giuseppe Ciampaglia, Linda Roland Danil, Enzo de Ianni, Giuseppe della Torre, Augusto De Toro, Basilio Di Martino, Germano Dottori, Antulio J. Echevarria II, Immacolata Eramo, Dario Fabbri, Marco Formisano, Mariano Gabriele, Giampiero Giacomello, Emilio Gin, Matteo Giurco, Virgilio Ilari, Carlo Jean, Juhász Balázs, Marco Leofrigio, Mark Mandeles, Wojciech Mazur, Riccardo Masini, Sergio Masini, Andrea Molinari, Claudio Nardi, Elena Piana, Giangiuseppe Pili, Giovanni Punzo, Stefano Rapisarda, Stefano Ruzza, Wilder Alejandro Sanchez, Aldo A. Settia, Enrico Silverio, Teresa Silverio, Gian Piero Siroli, Donato Tamblé, Germana Tappero Merlo, Eric Robert Terzuolo, Ubong Essien Umoh, Maurizio Zinni
In this paper the naval power during the Persian Wars is analyzed an compared with the acquisitio... more In this paper the naval power during the Persian Wars is analyzed an compared with the acquisitions of the current age
In this paper are presented the results of anti-aircraft Itlian artillery in the period 1940-1943-