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M. Žamboch
M. Žamboch
Materials science
Metallurgy
Nuclear engineering
Reactor pressure vessel
Alloy
3
Papers
1
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0
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Assessment of WWER Reactor Pressure Vessel Internals and Program of Lifetime Management
2013
M. Ruščák
M. Žamboch
O. Erben
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13 – Crack growth behaviour of low-alloy steels for pressure boundary components under transient light water reactor operating conditions – CASTOC, Part 2: VVER conditions
2007
M. Ernestová
M. Žamboch
B. Devrient
A. Roth
U Ehrnsten
J. Fohl
Thomas Weissenberg
D. Gomézbriceño
J. Lapeña
S. Ritter
H.‐P. Seifert
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NRI experimental facility for the testing of irradiation assisted stress corrosion cracking
1998
M. Ruščák
P. Chvatal
M. Žamboch
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