Search Results - "Bonal, J.P"

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  1. 1

    Determination of the lithium diffusion coefficient in irradiated boron carbide pellets by Deschanels, X., Simeone, D., Bonal, J.P.

    Published in Journal of nuclear materials (01-03-1999)
    “…During neutron irradiation, 10B atoms in B 4C are destroyed, producing lithium and helium atoms according to the well-known 10B(n,α) 7Li reaction. The aim of…”
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    Journal Article
  2. 2

    Carbon fiber composites application in ITER plasma facing components by Barabash, V, Akiba, M, Bonal, J.P, Federici, G, Matera, R, Nakamura, K, Pacher, H.D, Rödig, M, Vieider, G, Wu, C.H

    Published in Journal of nuclear materials (01-10-1998)
    “…Carbon Fiber Composites (CFCs) are one of the candidate armour materials for the plasma facing components of the International Thermonuclear Experimental…”
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    Journal Article
  3. 3

    Progress of the European R&D on plasma–wall interactions, neutron effects and tritium removal in ITER plasma facing materials by Wu, C.H., Alessandrini, C., Bonal, J.P., Davis, J.W., Haasz, A.A., Jacob, W., Kallenbach, A., Keinonen, J., Kornejew, P., Moormann, R., Philipps, V., Roth, J., Scaffidi-Argentina, F., Würz, H.

    Published in Fusion engineering and design (01-10-2001)
    “…In a next step D/T fusion device like ITER, an intense neutron flux will be produced as a consequence of the nuclear fusion reactions. The effects of the…”
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    Journal Article Conference Proceeding
  4. 4

    Design requirements for SiC/SiC composites structural material in fusion power reactor blankets by Giancarli, L, Bonal, J.P, Caso, A, Le Marois, G, Morley, N.B, Salavy, J.F

    Published in Fusion engineering and design (01-09-1998)
    “…This paper recalls the main features of the TAURO blanket, a self-cooled Pb-17Li concept using SiC/SiC composites as structural material, developed for FPR…”
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    Journal Article Conference Proceeding
  5. 5

    Simulation experimental investigation of plasma off-normal events on advanced silicon doped CFC-NS31 by Bonal, J.P, Wu, C.H, Gosset, D

    Published in Journal of nuclear materials (01-12-2002)
    “…Fusion devices high heat loading due to off-normal events (e.g., plasma disruption, slow transients and ELMs, which can occur during a transition from detached…”
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    Journal Article
  6. 6

    Nuclear microprobe analysis of 7Li profile induced in HfB 2 by a neutron irradiation by Simeone, D., Deschanels, X., Gosset, D., Bonal, J.P., Berthoumieux, E.

    Published in Journal of nuclear materials (2001)
    “…HfB 2, a solid poor in boron, was irradiated by thermal neutrons in an experimental reactor. Using a nuclear microprobe, we have tracked lithium atoms produced…”
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    Journal Article
  7. 7

    Conceptual design of a high temperature water-cooled divertor for a fusion power reactor by Giancarli, L., Bonal, J.P., Puma, A. Li, Michel, B., Sardain, P., Salavy, J.F.

    Published in Fusion engineering and design (01-11-2005)
    “…This paper presents the conceptual design of a water-cooled divertor target using EUROFER as structural material, water coolant pressure and outlet…”
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    Journal Article Conference Proceeding
  8. 8

    Neutron irradiation effects on carbon based materials at 350°C and 800°C by Bonal, J.P, Wu, C.H

    Published in Journal of nuclear materials (2000)
    “…An experimental study on the neutron irradiation induced thermal properties and dimensional changes of various carbon based materials has been carried using…”
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    Journal Article
  9. 9

    Neutron induced thermal properties changes in carbon fiber composites irradiated from 600 to 1000°C by Bonal, J.P., Wu, C.H.

    Published in Journal of nuclear materials (02-06-1996)
    “…An experimental study on the neutron irradiation induced thermal properties changes of various carbon fiber composites has been carried out using the High Flux…”
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    Journal Article
  10. 10
  11. 11

    Neutron irradiation effects on the thermal conductivity and dimensional stability of carbon fiber composites at divertor conditions by Bonal, J.P., Wu, C.H.

    Published in Journal of nuclear materials (01-03-1996)
    “…In continuation of our study on neutron induced property changes of carbon fiber composites at low irradiation temperatures and low neutron doses, an…”
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    Journal Article
  12. 12

    Neutron effects on properties and annealing of low-Z materials by Wu, C.H., Bonal, J.P., Werle, H.

    Published in Fusion engineering and design (01-11-2000)
    “…Among the low-Z materials, carbon and beryllium are seriously considered as plasma facing materials (PFC) for the next step fusion experimental reactor,…”
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    Journal Article Conference Proceeding
  13. 13

    EU results on neutron effects on PFC materials by Wu, C.H., Bonal, J.P., Kwast, H., Moons, F., Pott, G., Werle, H., Vieider, G.

    Published in Fusion engineering and design (01-09-1998)
    “…Among the low-Z materials, carbon and beryllium are primary candidates for use as plasma facing materials for the International Thermonuclear Experimental…”
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    Journal Article Conference Proceeding
  14. 14

    European development of the ITER divertor target by Vieider, G, Merola, M, Bonal, J.P, Chappuis, P, Duglué, D, Duwe, R, Escourbiac, F, Fèbvre, M, Giancarli, L, Grattarola, M, LeMarois, G, Pacher, H.D, Pizzuto, A, Plöchl, L, Riccardi, B, Rödig, M, Schlosser, J, Smid, I, Tramier, P, Wu, C.H

    Published in Fusion engineering and design (01-11-1999)
    “…The main European contribution to the ITER divertor project was the development of the divertor target with severe operating requirements such as peak heat…”
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    Journal Article Conference Proceeding
  15. 15

    European development of prototypes for ITER high heat flux components by Vieider, G, Merola, M, Anselmi, F, Bonal, J.P, Chappuis, P, Dell'Orco, G, Duglué, D, Duwe, R, Erskine, S, Escourbiac, F, Fèbvre, M, Giancarli, L, Grattarola, M, LeMarois, G, Pacher, H.D, Pizzuto, A, Plöchl, L, Riccardi, B, Rödig, M, Schlosser, J, Salito, A, Schedler, B, Wu, C.H

    Published in Fusion engineering and design (01-11-2000)
    “…The extensive EU research and development, on international thermonuclear experimental reactor (ITER) high heat flux (HHF) components aims at the demonstration…”
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    Journal Article Conference Proceeding