In the present studies, the thermal behaviour of NaUO2BO3 has been investigated. This compound is a potential product of interaction between the coolant (Na), control rods (B4C), and the oxide fuel, which could form under accidental conditions in sodium-cooled fast reactors. The thermal expansion, the heat capacity, and thermal diffusivity of NaUO2BO3 have been measured. The thermal conductivity of the material is derived from these results and presented here for the first time.
POPA Karin;
BENES Ondrej;
STAICU Dragos;
GRIVEAU Jean-Christophe;
COLINEAU Eric;
SEIBERT Alice;
COLLE Jean-Yves;
STOHR Sarah;
RAISON Philippe;
SOMERS Joseph;
KONINGS Rudy;
2018-03-14
SPRINGER
JRC107059
1388-6150,
https://publications.jrc.ec.europa.eu/repository/handle/JRC107059,
10.1007/s10973-017-6923-y,
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