Articles in Scholarly Journals [Incomplete List]

1. On the effects of the supporting frame on the radiation-induced damage of HCLL-TBM structural material
   Journal of Nuclear Materials, vol. 367-370, pp. 1344–1349, 2007
2. Progress in the benchmark exercise for analyzing the lithiate breeder pebble bed thermo-mechanical behaviour
   Fusion Engineering and Design, vol. 81, no. 1-7, pp. 169–174, 2006
3. Estimating radiant fields in flat heterogeneous photoreactors by the six-flux model
   AIChE Journal, vol. 52, no. 11, pp. 3882–3890, 2006
4. On the influence of the supporting frame on the nuclear response of the Helium-Cooled Lithium Lead Test Blanket Module for ITER
   Fusion Engineering and Design, vol. 81, no. 1-7, pp. 677–686, 2006
5. Mixed MHD convection and Tritium transport in fusion-relevant configurations
   Fusion Engineering and Design, vol. 75-79, pp. 697–702, 2005
6. On the nuclear response of the helium-cooled lithium lead test blanket module in ITER
   Fusion Engineering and Design, vol. 75-79, pp. 725–730, 2005
7. Steady state and transient thermal–hydraulic analyses on ITER divertor module
   Fusion Engineering and Design, vol. 75-79, pp. 457–461, 2005
8. Thermo-mechanical testing of Li?ceramic for the helium cooled pebble bed (HCPB) breeding blanket
   Journal of Nuclear Materials, vol. 329-333, pp. 1305–1308, 2004
9. On the nuclear response of the water-cooled Pb–17Li test blanket module for ITER-FEAT
   Fusion Engineering and Design, vol. 69, no. 1-4, pp. 469–477, 2003
10. Experimental tests on Li-ceramic breeders for the helium cooled pebble bed (HCPB) blanket design
    Fusion Engineering and Design, vol. 69, no. 1-4, pp. 233–240, 2003
11. Neutronic and photonic analysis of the water-cooled Pb_17Li test blanket module for ITER-FEAT
    Fusion Engineering and Design, vol. 61-62, pp. 439–447, 2002
12. Further improvements of the water-cooled Pb–17Li blanket
    Fusion Engineering and Design, vol. 58-59, pp. 523–527, 2001
13. Modelling of the thermal-mechanical behaviour of a single size beryllium pebble bed
    Fusion Engineering and Design, vol. 58-59, pp. 635–640, 2001
14. Potential and limits of water-cooled Pb–17Li blankets and divertors for a fusion power plant
    Fusion Engineering and Design, vol. 49-50, no. 1-4, pp. 543–549, 2000
15. On the use of tin?lithium alloys as breeder material for blankets of fusion power plants
    Journal of Nuclear Materials, vol. 283-287, pp. 1375–1379, 2000
16. Water-cooled Pb?17Li test blanket module for ITER: Impact of the structural material grade on the neutronic responses
    Journal of Nuclear Materials, vol. 258-263, pp. 357–361, 1998
17. Neutronic and photonic analysis of the single box water-cooled lithium lead blanket for a DEMO reactor
    Fusion Engineering and Design, vol. 41, no. 1-4, pp. 577–582, 1998