K. Šplíchal

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

J.-F. Salavy, G. Aiello, Olivier David et al. · Fusion Engineering and Design · 2008 · 48 citations

Engineering, Electrical Engineering, Systems Engineering +12

The EU TBM systems: Design and development programme

L.V. Boccaccini, J.-F. Salavy, O. Bede et al. · Fusion Engineering and Design · 2009 · 48 citations

Engineering, Systems Engineering, Systems Architecture +4

Combination of radiation and hydrogen damage of reactor pressure vessel materials

K. Šplíchal, M. Ruščák, J. Ẑďárek · International Journal of Pressure Vessels and Piping · 1993 · 18 citations

Engineering, Materials Science, Nuclear Engineering +14

Fracture toughness of the hydrogen charged EUROFER 97 RAFM steel at room temperature and 120°C

K. Šplíchal, Jan Berka, Jaroslav V. Burda et al. · Journal of Nuclear Materials · 2009 · 14 citations

Engineering, Materials Engineering, Materials Science +17

Hydrogen and radiation embrittlement of CrMoV and CrNiMoV ferritic RPV steels

J. Koutský, K. Šplíchal · International Journal of Pressure Vessels and Piping · 1986 · 12 citations

Engineering, Materials Engineering, Materials Science +14