J.F. Salavy: search on Z-Library

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1

Current material and design studies for the utilization of Li2ZrO3 in the BIT blanket concept

N. Roux, J. Mougin, B. Rasneur, E. Proust, L. Giancarli, J.F. Salavy

Journal:

Journal of Nuclear Materials

Year:

1994

Language:

english

File:

PDF, 663 KB

english, 1994

2

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

L. Giancarli, J.P. Bonal, A. Li Puma, B. Michel, P. Sardain, J.F. Salavy

Journal:

Fusion Engineering and Design

Year:

2005

Language:

english

File:

PDF, 116 KB

english, 2005

3

Tritium breeder blankets design and technologies in Europe: Development status of ITER Test Blanket Modules, test & qualification strategy and roadmap towards DEMO

Y. Poitevin, L.V. Boccaccini, M. Zmitko, I. Ricapito, J.-F. Salavy, E. Diegele, F. Gabriel, E. Magnani, H. Neuberger, R. Lässer, L. Guerrini

Journal:

Fusion Engineering and Design

Year:

2010

Language:

english

File:

PDF, 586 KB

english, 2010

4

Assessment of design limits and criteria requirements for Eurofer structures in TBM components

G. Aiello, J. Aktaa, F. Cismondi, G. Rampal, J.-F. Salavy, F. Tavassoli

Journal:

Journal of Nuclear Materials

Year:

2011

Language:

english

File:

PDF, 1.52 MB

english, 2011

5

Tauro: a ceramic composite structural material self-cooled Pb—17Li breeder blanket concept

A.S. Pérez Ramírez, A. Caso, L. Giancarli, N. Le Bars, G. Chaumat, J.F. Salavy, J. Szczepanski

Journal:

Journal of Nuclear Materials

Year:

1996

Language:

english

File:

PDF, 340 KB

english, 1996

6

R&D issues for SiCf/SiC composites structural material in fusion power reactor blankets

L Giancarli, G Aiello, A Caso, A Gasse, G Le Marois, Y Poitevin, J.F Salavy, J Szczepanski

Journal:

Fusion Engineering and Design

Year:

2000

Language:

english

File:

PDF, 174 KB

english, 2000

7

Development and qualification of functional materials for the EU Test Blanket Modules: Strategy and R&D activities

M. Zmitko, Y. Poitevin, L. Boccaccini, J.-F. Salavy, R. Knitter, A. Möslang, A.J. Magielsen, J.B.J. Hegeman, R. Lässer

Journal:

Journal of Nuclear Materials

Year:

2011

Language:

english

File:

PDF, 170 KB

english, 2011

8

[IEEE 15th IEEE/NPSS Symposium. Fusion Engineering - Hyannis, MA, USA (11-15 Oct. 1993)] 15th IEEE/NPSS Symposium. Fusion Engineering - The EC conceptual design proposal of a water-cooled convertible blanket for ITER

Giancarli, L., Proust, E., Baraer, L., Bielak, B., Quintric-Bossy, J., Raepsaet, X., Salavy, J.F., Sedano, L., Severi, Y., Szczepanski, J.

Year:

1994

Language:

english

File:

PDF, 608 KB

english, 1994

9

Tiles chamfering and power handling of the MK II HD divertor

J.-F. Salavy, P. Chappuis, P.J. Lomas, V. Riccardo

Journal:

Fusion Engineering and Design

Year:

2005

Language:

english

File:

PDF, 100 KB

english, 2005

10

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

A. Li Puma, J.L. Berton, B. Brañas, L. Bühler, J. Doncel, U. Fischer, W. Farabolini, L. Giancarli, D. Maisonnier, P. Pereslavtsev, S. Raboin, J.-F. Salavy, P. Sardain, J. Szczepanski, D. Ward

Journal:

Fusion Engineering and Design

Year:

2006

Language:

english

File:

PDF, 236 KB

english, 2006

11

Design approach for the main ITER test blanket modules for the EU helium cooled lithium–lead blankets

G. Rampal, D. Gatelet, L. Giancarli, G. Laffont, A. Li-Puma, J.F. Salavy, E. Rigal

Journal:

Fusion Engineering and Design

Year:

2006

Language:

english

File:

PDF, 285 KB

english, 2006

12

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

L.V. Boccaccini, J.-F. Salavy, R. Lässer, A. Li Puma, R. Meyder, H. Neuberger, Y. Poitevin, G. Rampal

Journal:

Fusion Engineering and Design

Year:

2006

Language:

english

File:

PDF, 320 KB

english, 2006

13

Overview of the last progresses for the European Test Blanket Modules projects

J.-F. Salavy, L.V. Boccaccini, R. Lässer, R. Meyder, H. Neuberger, Y. Poitevin, G. Rampal, E. Rigal, M. Zmitko, A. Aiello

Journal:

Fusion Engineering and Design

Year:

2007

Language:

english

File:

PDF, 274 KB

english, 2007

14

Thermal–hydraulic analysis of the HCLL DEMO blanket

G. Aiello, F. Gabriel, L. Giancarli, G. Rampal, J.-F. Salavy

Journal:

Fusion Engineering and Design

Year:

2007

Language:

english

File:

PDF, 408 KB

english, 2007

15

A 2D finite element modelling of tritium permeation for the HCLL DEMO blanket module

F. Gabriel, Y. Escuriol, F. Dabbene, O. Gastaldi, J.F. Salavy, L. Giancarli

Journal:

Fusion Engineering and Design

Year:

2007

Language:

english

File:

PDF, 737 KB

english, 2007

16

Manufacturing of a HCLL cooling plate mock up

Emmanuel Rigal, Guillaume de Dinechin, Gilles Rampal, Guy Laffont, Lionel Cachon, Jean-François Salavy, Yves Poitevin

Journal:

Fusion Engineering and Design

Year:

2008

Language:

english

File:

PDF, 1.46 MB

english, 2008

17

Blanket manufacturing technologies: Thermomechanical tests on helium cooled lithium lead (HCLL) blanket mocks up

G. Laffont, L. Cachon, P. Taraud, F. Challet, G. Rampal, E. Rigal, J.F. Salavy, Y. Poitevin

Journal:

Fusion Engineering and Design

Year:

2008

Language:

english

File:

PDF, 1.47 MB

english, 2008

18

Overview of liquid metal TBM concepts and programs

C.P.C. Wong, J.-F. Salavy, Y. Kim, I. Kirillov, E. Rajendra Kumar, N.B. Morley, S. Tanaka, Y.C. Wu

Journal:

Fusion Engineering and Design

Year:

2008

Language:

english

File:

PDF, 375 KB

english, 2008

19

Helium-cooled test blanket module box behaviour under accidental pressurisation

Christian Girard, Nicolas Schmidt, Jean-François Salavy, Gilles Rampal

Journal:

Fusion Engineering and Design

Year:

2008

Language:

english

File:

PDF, 531 KB

english, 2008

20

Thermo-hydraulical and thermo-mechanical analysis of the HCLL-TBM breeding unit

G. Aiello, F. Gabriel, L. Giancarli, G. Rampal, J.-F. Salavy

Journal:

Fusion Engineering and Design

Year:

2008

Language:

english

File:

PDF, 882 KB

english, 2008

21

Tritium transfers and main operating parameters impact for demo lithium lead breeding blanket (HCLL)

Olivier Gastaldi, Nicolas Ghirelli, Franck Gabriel, Luciano Giancarli, Jean François Salavy

Journal:

Fusion Engineering and Design

Year:

2008

Language:

english

File:

PDF, 792 KB

english, 2008

22

A new cooling scheme for the HCLL TBM

G. Aiello, F. Gabriel, G. Rampal, J.-F. Salavy

Journal:

Fusion Engineering and Design

Year:

2009

Language:

english

File:

PDF, 1.08 MB

english, 2009

23

Engineering studies for integration of the test blanket module (TBM) systems inside an ITER equatorial port plug

S. Madeleine, A. Saille, J.-P. Martins, J.-F. Salavy, N. Jonquères, G. Rampal, O. Bede, H. Neuberger, L. Boccaccini, L. Doceul

Journal:

Fusion Engineering and Design

Year:

2009

Language:

english

File:

PDF, 1.03 MB

english, 2009

24

The EU TBM systems: Design and development programme

L.V. Boccaccini, J.-F. Salavy, O. Bede, H. Neuberger, I. Ricapito, P. Sardain, L. Sedano, K. Splichal

Journal:

Fusion Engineering and Design

Year:

2009

Language:

english

File:

PDF, 1.14 MB

english, 2009

25

A methodology to assess the impact of the manufacturing margins of the HCLL-TBM first wall in the design criteria

F. Gabriel, G. Aiello, J.-F. Salavy

Journal:

Fusion Engineering and Design

Year:

2009

Language:

english

File:

PDF, 597 KB

english, 2009

26

The ancillary systems of the European test blanket modules: Configuration and integration in TIER

I. Ricapito, O. Bede, L.V. Boccaccini, A. Ciampichetti, B. Ghidersa, L. Guerrini, R. Lässer, H. Neuberger, Y. Poitevin, J.F. Salavy

Journal:

Fusion Engineering and Design

Year:

2010

Language:

english

File:

PDF, 806 KB

english, 2010

27

Transient thermo-hydraulical/thermo-mechanical analysis of the HCLL-TBM for ITER

G. Aiello, F. Gabriel, A. Li-Puma, A. Pajot, G. Rampal, J.-F. Salavy, H. Simon

Journal:

Fusion Engineering and Design

Year:

2010

Language:

english

File:

PDF, 1.79 MB

english, 2010

28

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

A. Li Puma, G. Aiello, F. Gabriel, G. Laffont, G. Rampal, J.-F. Salavy

Journal:

Fusion Engineering and Design

Year:

2010

Language:

english

File:

PDF, 375 KB

english, 2010

29

Performance of the TAURO blanket system associated with a liquid-metal cooled divertor

H Golfier, G Aiello, M.A Fütterer, A Gasse, L Giancarli, Y Poitevin, J.F Salavy, Y Severi, J Szczepanski

Journal:

Fusion Engineering and Design

Year:

2000

Language:

english

File:

PDF, 211 KB

english, 2000

30

Modeling of SiCf/SiC composite structures for nuclear components

G. Aiello, H. Golfier, J.-F. Maire, Y. Poitevin, J.-F. Salavy

Journal:

Fusion Engineering and Design

Year:

2000

Language:

english

File:

PDF, 100 KB

english, 2000

31

Manufacturing of a full scale baffle prototype for ITER with a CFC and W plasma spray armour

M Merola, I Bobin-Vastra, A Cardella, M Febvre, L Giancarli, L Plöchl, J.F Salavy, A Salito, B Schedler, G Vieider

Journal:

Fusion Engineering and Design

Year:

2000

Language:

english

File:

PDF, 311 KB

english, 2000

32

Evaluation of divertor conceptual designs for a fusion power plant

M. Ferrari, L. Giancarli, K. Kleefeldt, C. Nardi, M. Rödig, J. Reimann, J.F. Salavy

Journal:

Fusion Engineering and Design

Year:

2001

Language:

english

File:

PDF, 318 KB

english, 2001

33

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

Fütterer, M.A, Benamati, G, Ricapito, I, Giancarli, L, Le Marois, G, Li Puma, A, Poitevin, Y, Reimann, J, Salavy, J.-F, Szczepanski, J, Vella, G, Ruvutuso, G

Journal:

Fusion Engineering and Design

Year:

2001

Language:

english

File:

PDF, 168 KB

english, 2001

34

The EU advanced lead lithium blanket concept using SiCf/SiC flow channel inserts as electrical and thermal insulators

Norajitra, P., Bühler, L., Fischer, U., Kleefeldt, K., Malang, S., Reimann, G., Schnauder, H., Giancarli, L., Golfier, H., Poitevin, Y., Salavy, J.F.

Journal:

Fusion Engineering and Design

Year:

2001

Language:

english

File:

PDF, 268 KB

english, 2001

35

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

Y Poitevin, M.A Fütterer, L Giancarli, A Li Puma, J.-F Salavy, J Szczepanski

Journal:

Fusion Engineering and Design

Year:

2002

Language:

english

File:

PDF, 217 KB

english, 2002

36

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

A Li Puma, L Giancarli, Y Poitevin, J.-F Salavy, P Sardain, J Szczepanski

Journal:

Fusion Engineering and Design

Year:

2002

Language:

english

File:

PDF, 290 KB

english, 2002

37

Analysis of high heat flux testing of mock-ups

J.-F. Salavy, L. Giancarli, M. Merola, F. Picard, M. Rödig

Journal:

Fusion Engineering and Design

Year:

2003

Language:

english

File:

PDF, 370 KB

english, 2003

38

The design of a new JET divertor for high triangularity and high current scenarios

P. Chappuis, C. Damiani, C. Guerin, F. Hurd, A. Loarte, P. Lomas, A. Lorenz, J. Paméla, A. Peacock, C. Portafaix, J. Rapp, V. Riccardo, F. Rimini, G. Saibene, J.F. Salavy, Y. Sauce, R. Sartori, E. Sol

Journal:

Fusion Engineering and Design

Year:

2003

Language:

english

File:

PDF, 405 KB

english, 2003

39

Design requirements for SiC/SiC composites structural material in fusion power reactor blankets

L Giancarli, J.P Bonal, A Caso, G Le Marois, N.B Morley, J.F Salavy

Journal:

Fusion Engineering and Design

Year:

1998

Language:

english

File:

PDF, 248 KB

english, 1998

40

Design development and manufacturing sequence of the European water-cooled Pb-17Li test blanket module

M.A Fütterer, B Bielak, J.P Deffain, C Dellis, L Giancarli, A Li Puma, C Nardi, J.F Salavy, K Schleisiek, J Szczepanski

Journal:

Fusion Engineering and Design

Year:

1998

Language:

english

File:

PDF, 172 KB

english, 1998

41

ITER baffle module small-scale mock-ups: First Wall thermo-mechanical testing results

Y. Severi, P. Chappuis, L. Giancarli, G. Le Marois, Y. Poitevin, M. Rödig, J.F. Salavy, G. Vieider

Journal:

Fusion Engineering and Design

Year:

1998

Language:

english

File:

PDF, 352 KB

english, 1998

42

Objectives feasibility assessment of the water-cooled lithium–lead mock-up testing in ITER

L Giancarli, G Benamati, B Bielak, M.A Fütterer, G Marbach, C Nardi, O Ogorodnikova, Y Poitevin, J Reimann, J F. Salavy, Y Severi, J Szczepanski

Journal:

Fusion Engineering and Design

Year:

1999

Language:

english

File:

PDF, 153 KB

english, 1999

43

Convertible liquid metal blankets for ITER with Pb-17Li as breeding material

J Reimann, L Giancarli, S Malang, L Petrizzi, E Proust, J.F Salavy, K Schleisiek

Journal:

Fusion Engineering and Design

Year:

1995

Language:

english

File:

PDF, 707 KB

english, 1995

44

The test blanket modules project in Europe: From the strategy to the technical plan over next 10 years

Y. Poitevin, L.V. Boccaccini, G. Dell’Orco, E. Diegele, R. Lässer, J.-F. Salavy, J. Sundström, M. Zmitko

Journal:

Fusion Engineering and Design

Year:

2007

Language:

english

File:

PDF, 401 KB

english, 2007

45

The HCLL Test Blanket Module system: Present reference design, system integration in ITER and R&D needs

J.-F. Salavy, G. Aiello, O. David, F. Gabriel, L. Giancarli, C. Girard, N. Jonquères, G. Laffont, S. Madeleine, Y. Poitevin, G. Rampal, I. Ricapito, K. Splichal

Journal:

Fusion Engineering and Design

Year:

2008

Language:

english

File:

PDF, 339 KB

english, 2008

46

Failure mode and effect analysis for the European test blanket modules

T. Pinna, L.V. Boccaccini, J.F. Salavy

Journal:

Fusion Engineering and Design

Year:

2008

Language:

english

File:

PDF, 123 KB

english, 2008

47

Must we use ferritic steel in TBM?

J.-F. Salavy, L.V. Boccaccini, P. Chaudhuri, S. Cho, M. Enoeda, L.M. Giancarli, R.J. Kurtz, T.Y. Luo, K. Bhanu Sankara Rao, C.P.C. Wong

Journal:

Fusion Engineering and Design

Year:

2010

Language:

english

File:

PDF, 136 KB

english, 2010

48

Hydrogen isotope permeation through and inventory in the first wall of the water cooled Pb–17Li blanket for DEMO

O.V. Ogorodnikova, M.A. Fütterer, E. Serra, G. Benamati, J.-F. Salavy, G. Aiello

Journal:

Journal of Nuclear Materials

Year:

1999

Language:

english

File:

PDF, 283 KB

english, 1999

49

Potential and limits of water-cooled Pb–17Li blankets and divertors for a fusion power plant

M.A Fütterer, L Barleon, L Giancarli, A.Li Puma, O.V Ogorodnikova, Y Poitevin, J.F Salavy, J Szczepanski, G Vella

Journal:

Fusion Engineering and Design

Year:

2000

Language:

english

File:

PDF, 179 KB

english, 2000

50

Ferritic–Martensitic steel Test Blanket Modules: Status and future needs for design criteria requirements and fabrication validation

J.-F. Salavy, G. Aiello, P. Aubert, L.V. Boccaccini, M. Daichendt, G. De Dinechin, E. Diegele, L.M. Giancarli, R. Lässer, H. Neuberger, Y. Poitevin, Y. Stephan, G. Rampal, E. Rigal

Journal:

Journal of Nuclear Materials

Year:

2009

Language:

english

File:

PDF, 289 KB

english, 2009