Baudouin Arien

Person

Arien, Baudouin

Person

  1. 2013
  2. The issue of accelerator beam trips for efficient ADS operation

    Rimpault, G., Darde, P., Mellier, F., Dagan, R., Schikorr, M., Weisenburger, A., Maes, D., Sobolev, V., Arien, B., Lamberts, D., De Bruyn, D., Mueller, A. C., Biarrotte, J-L. & Michiels, S., Nov 2013, In : Nuclear Technology. 184, 2, p. 249-260

    Research output: Contribution to journalArticle

  3. The MYRRHA-FASTEF cores design for critical and sub-critical operational modes (EU FP7 Central Design Team project)

    Sarotto, M., Castelliti, D. & Arien, B., Aug 2013, In : Nuclear Engineering and Design. 265, p. 184-200

    Research output: Contribution to journalArticle

  4. MYRRHA/FASTEF Safety Analysis in Sub-critical and Critical Mode

    Castelliti, D. & Arien, B., 13 May 2013, NURETH-15 Book of Abstracts. Pisa, Italy, Vol. 1. p. 375-375

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

  5. 2009
  6. DOMAIN III: HYBRID SYSTEM WITH FERTILE FUEL (MYRRHA design concept)

    Malambu Mbala, E., Arien, B., Da Cruz, D. F., Wider, H. & Heusdains, S., Sep 2009, Advanced Reactor technology Options for Utilization and Transmutation of Actinides in Spent Nuclear Fuel. 1 ed. Vienna, Austria: IAEA - International Atomic Energy Agency, Vol. 1. p. 46-73 (International Atomic Energy Agency Technical Documents; no. IAEA-TECDOC-1626).

    Research output: Contribution to report/book/conference proceedingsChapter

  7. GCFR Coupled Neutronic and Thermal-Fluid-Dynamics Analyses for a Core Containing Minor Actinides

    Castelliti, D., Bomboni, E., Cerullo, N., Lomonaco, G., Parisi, C. & Arien, B., 2 Mar 2009, In : Science and Technology of Nuclear Installations. 2009, 1, p. 1-8

    Research output: Contribution to journalArticle

  8. 2008
  9. Design and safety studies on an EFIT core with CERMET fuel

    Chen, X-N., Rineiski, A., Liu, P., Maschek, W., Matzerath Boccaccini, C., Gabrielli, F., Sobolev, V. & Arien, B., Sep 2008, Proceedings of "International Conference on the Physics of Reactors -PHYSOR 2008". France, p. FP1821-FP1828

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

  10. 2007
  11. First results of safety analysis for ADTs with CERCEZR and CERMET fuels within EUROTRANS-AFTRA project

    Maschek, W., Cheng, X., Matzerath Boccaccini, C., Rineiski, A., Sobolev, V., Smith, P., Thetford, R., Wallenius, J., Delage, F., Ottaviani, J-P., Pillon, S., Haas, D. & Arien, B., 30 Oct 2007, Actinide and Fission Product Partitioning and Transmutation. Ninth Information Exchange Meeting.. Paris, France, p. 137-148

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

  12. 2001
  13. MYRRHA, a multipurpose accelerator driven system for R&D

    Aït Abderrahim, H., Malambu Mbala, E., Kupschusp, P., Benoit, P., Van Tichelen, K., Arien, B., Vermeersch, F., Jongen, Y. & Vandeplassche, D., 4 Jun 2001, Proceedings of the International Joint Power Generation Conference-Power and Nuclear . ASME - The American Society of Mechanical Engineers, 6 p.

    Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

  14. 1986
  15. CASSANDRE: A two-dimensional multigroup diffusion code for reactor transient analysis - Code description and user's guide

    Arien, B. & Daniëls, A., 1986, Mol, Belgium: Studiecentrum voor Kernenergie. (SCK•CEN Reports; no. BLG-591)

    Research output: Report/bookBLG - Open report

  16. 1984
  17. CASSANDRE: A two-dimensional multigroup diffusion code for reactor transients analysis

    Arien, B., Siebertz, A. & et al., 1984, Mol, Belgium: Studiecentrum voor Kernenergie. (SCK•CEN Reports; no. BLG-571)

    Research output: Report/bookBLG - Open report

ID: 26748