K. Pytel

CERCA LEU fuel assemblies testing in Maria Reactor - safety analysis summary and testing program scope.

N. A. Hanan, P. L. Garner, K. Pytel, 2010 .

Wpływ komponentów na parametry betonów chudych w podbudowach drogowych

K. Pytel, P. Trybalski, 2013 .

Delayed Gamma Measurements in Different Nuclear Research Reactors Bringing Out the Importance of Their Contribution in Gamma Flux Calculations

D. Fourmentel, L. Snoj, K. Pytel, 2015, IEEE Transactions on Nuclear Science.

Principle of calibration of the simple calorimeter for nuclear heating measurements in MARIA reactor and transposition to the case of JHR reactor

G. Bignan, A. Lyoussi, C. Gonnier, 2013, 2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA).

Structural, thermal expansion and heat capacity study of lead-free [(1 − x)(Na0.5Bi0.5)–xBa]Zr1−yTiyO3 ceramics

K. Pytel, W. Hofmeister, J. Suchanicz, 2010 .

Processing, basic characterization and standard dielectric measurements on PLZT x/65/35 (4 ≤ x ≤ 11) ceramics

M. Livinsh, Andris Sternberg, K. Pytel, 2014 .

Dielectric properties of PLZT-x/65/35 (2 \leqslant x \leqslant 13) under mechanical stress, electric field and temperature loading

M. Livinsh, K. Pytel, J. Suchanicz, 2013 .

Enhancement of critical current density in fast neutron irradiated melt-textured YBa2Cu3O7-x

Henryk Szymczak, Zhou Lian, Zhang Pingxiang, 1993 .