A. Puma

发表

Developing structural, high-heat flux and plasma facing materials for a near-term DEMO fusion power plant: The EU assessment

P. F. Morris, B. Raj, S. Zinkle, 2014, 1408.3546.

Power plant conceptual studies in Europe

P. Sardain, L. Di Pace, D. Ward, 2007 .

Conceptual design of a high temperature water-cooled divertor for a fusion power reactor

P. Sardain, L. Giancarli, A. Puma, 2005 .

Assessment of an ITER-like water-cooled divertor for DEMO

A. Puma, M. Richou, E. Visca, 2013, 2013 IEEE 25th Symposium on Fusion Engineering (SOFE).

Evaluation of nuclear heating, tritium breeding and shielding efficiency of the DEMO HCLL breeder blanket

U. Fischer, A. Puma, A. Cardella, 2005 .

Tokamak D-T neutron source models for different plasma physics confinement modes

Rosaria Villari, Antonella Li Puma, Clement Fausser, 2012 .

TRIPOLI-4® Monte Carlo code ITER A-lite neutronic model validation

Jean-Charles Jaboulay, J. C. Trama, Antonella Li Puma, 2014 .

1 FTP / 4-4 Rb ACTIVITIES ON THE HELIUM COOLED LITHIUM LEAD TEST BLANKET MODULE FOR ITER

P. Sardain, D. Keller, A. Puma, 2012 .

Power plant conceptual study: WCLL concept

David Ward, Yves Poitevin, L. Giancarli, 2003 .

Status of the design and performances of the WCLL test blanket module for ITER-FEAT

L. Giancarli, A. Puma, J. Salavy, 2002 .

The European power plant conceptual study: Helium-cooled lithium–lead reactor concept

P. Sardain, D. Ward, L. Giancarli, 2006 .

On the use of tin–lithium alloys as breeder material for blankets of fusion power plants

P. Sardain, L. Giancarli, A. Puma, 2000 .

Materials RD for a timely DEMO: Key findings and recommendations of the EU Roadmap Materials Assessment Group

Steven J. Zinkle, David Ward, Mark R. Gilbert, 2014 .

The manufacturing technologies of the European breeding blankets

E. Diegele, Yves Poitevin, A. Cardella, 2004 .

HCLL TBM design status and development

J.-F. Salavy, F. Gabriel, Giacomo Aiello, 2011 .

Requirements and proposals for control and monitoring measurements of the HCLL TBM

J.-F. Salavy, F. Gabriel, Giacomo Aiello, 2010 .

Development of the Helium Cooled Lithium Lead blanket for DEMO

Giacomo Aiello, N. Jonquères, G. Rampal, 2014 .

Physics basis and mechanical design of the actively cooled duct scraper protection for the JET neutral beam enhancement

E. Surrey, T. Jones, D. Ćirić, 2007 .

Initial DEMO tokamak design configuration studies

Massimiliano Mattei, G. Federici, Antony Loving, 2015 .

Status of the EU DEMO breeding blanket manufacturing R&D activities

J. Aktaa, L. Savoldi, L. Boccaccini, 2020 .

Overview of the JET neutral beam enhancement project

C. D. Challis, S. J. Cox, Elizabeth Surrey, 2007 .

Further improvements of the water-cooled Pb-17Li blanket

M. A. Fütterer, Yves Poitevin, J.-F. Salavy, 2001 .

HCLL TBM for ITER-design studies

Yves Poitevin, G. Rampal, Emmanuel Rigal, 2005 .

Tritium control modelling for a helium cooled lithium–lead blanket of a fusion power reactor

M. A. Fütterer, Andrea Ciampichetti, I. Ricapito, 2006 .

Breeding blanket design and systems integration for a helium-cooled lithium–lead fusion power plant

David Ward, Ulrich Fischer, J.-F. Salavy, 2006 .

Optimization of the first wall for the DEMO water cooled lithium lead blanket

Christian Bachmann, Antonella Li Puma, Giacomo Aiello, 2015 .

Potential performances of a divertor concept based on liquid metal cooled SiCf/SiC structures

L. Giancarli, A. Puma, H. Golfier, 2003 .

Optimization of a water-cooled divertor for the European power plant conceptual study

Yves Poitevin, J.-F. Salavy, L. Giancarli, 2002 .

Test blanket modules (ITER) and breeding blanket (DEMO): History of major fabrication technologies development of HCLL and HCPB and status

M. Zmitko, Antonella Li Puma, Noel Thomas, 2020 .

The European test blanket module systems: Design and integration in ITER

Yves Poitevin, L. V. Boccaccini, J.-F. Salavy, 2006 .