The WEST project: Testing ITER divertor high heat flux component technology in a steady state tokamak environment

J. Bucalossi, M. Missirlian, P. Moreau, F. Samaille, E. Tsitrone, D. van Houtte, T. Batal, C. Bourdelle, M. Chantant, Y. Corre, X. Courtois, L. Delpech, L. Doceul, D. Douai, H. Dougnac, F. Faïsse, C. Fenzi, F. Ferlay, M. Firdaouss, L. Gargiulo, P. Garin, C. Gil, A. Grosman, D. Guilhem, J. Gunn, C. Hernandez, D. Keller, S. Larroque, M. Lipa, P. Lotte, A. Martinez, O. Meyer, F. Micolon, P. Mollard, E. Nardon, R. Nouailletas, M. Richou, S. Salasca, J.-M. Travère

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DOI: 10.1016/j.fusengdes.2014.01.062
Published: 2014-02-22
Container: Fusion Engineering and Design
Publisher: Not recorded
Open access: no

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Cite this work

BibTeX

@article{allodium:10.1016/j.fusengdes.2014.01.062,
  title = {The WEST project: Testing ITER divertor high heat flux component technology in a steady state tokamak environment},
  author = {J. Bucalossi and M. Missirlian and P. Moreau and F. Samaille and E. Tsitrone and D. van Houtte and T. Batal and C. Bourdelle and M. Chantant and Y. Corre and X. Courtois and L. Delpech and L. Doceul and D. Douai and H. Dougnac and F. Faïsse and C. Fenzi and F. Ferlay and M. Firdaouss and L. Gargiulo and P. Garin and C. Gil and A. Grosman and D. Guilhem and J. Gunn and C. Hernandez and D. Keller and S. Larroque and M. Lipa and P. Lotte and A. Martinez and O. Meyer and F. Micolon and P. Mollard and E. Nardon and R. Nouailletas and M. Richou and S. Salasca and J.-M. Travère},
  year = {2014},
  journal = {Fusion Engineering and Design},
  doi = {10.1016/j.fusengdes.2014.01.062},
  url = {https://doi.org/10.1016/j.fusengdes.2014.01.062}
}

RIS

TY  - JOUR
TI  - The WEST project: Testing ITER divertor high heat flux component technology in a steady state tokamak environment
AU  - J. Bucalossi
AU  - M. Missirlian
AU  - P. Moreau
AU  - F. Samaille
AU  - E. Tsitrone
AU  - D. van Houtte
AU  - T. Batal
AU  - C. Bourdelle
AU  - M. Chantant
AU  - Y. Corre
AU  - X. Courtois
AU  - L. Delpech
AU  - L. Doceul
AU  - D. Douai
AU  - H. Dougnac
AU  - F. Faïsse
AU  - C. Fenzi
AU  - F. Ferlay
AU  - M. Firdaouss
AU  - L. Gargiulo
AU  - P. Garin
AU  - C. Gil
AU  - A. Grosman
AU  - D. Guilhem
AU  - J. Gunn
AU  - C. Hernandez
AU  - D. Keller
AU  - S. Larroque
AU  - M. Lipa
AU  - P. Lotte
AU  - A. Martinez
AU  - O. Meyer
AU  - F. Micolon
AU  - P. Mollard
AU  - E. Nardon
AU  - R. Nouailletas
AU  - M. Richou
AU  - S. Salasca
AU  - J.-M. Travère
PY  - 2014
JO  - Fusion Engineering and Design
DO  - 10.1016/j.fusengdes.2014.01.062
UR  - https://doi.org/10.1016/j.fusengdes.2014.01.062
ER  -

APA

Bucalossi, J., Missirlian, M., Moreau, P., Samaille, F., Tsitrone, E., Houtte, D. V., Batal, T., Bourdelle, C., Chantant, M., Corre, Y., Courtois, X., Delpech, L., Doceul, L., Douai, D., Dougnac, H., Faïsse, F., Fenzi, C., Ferlay, F., Firdaouss, M., Gargiulo, L., Garin, P., Gil, C., Grosman, A., Guilhem, D., Gunn, J., Hernandez, C., Keller, D., Larroque, S., Lipa, M., Lotte, P., Martinez, A., Meyer, O., Micolon, F., Mollard, P., Nardon, E., Nouailletas, R., Richou, M., Salasca, S., & Travère, J. (2014). The WEST project: Testing ITER divertor high heat flux component technology in a steady state tokamak environment. Fusion Engineering and Design. https://doi.org/10.1016/j.fusengdes.2014.01.062

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hal · retrieved 2026-09-25T04:47:16.643Z