Ruthenium behavior in the reactor cooling system in case of a PWR severe accident

In the frame of severe accident topic for pressurized water reactor, the physical-chemistry of Ru fission products were experimentally studied to better understand their behavior inside the reactor coolant system in air or air/steam atmospheres. The tests consisted in vaporizing RuO 2 at 1200 °C and...

Full description

Saved in:
Bibliographic Details
Published inJournal of radioanalytical and nuclear chemistry Vol. 316; no. 1; pp. 161 - 177
Main Authors Ohnet, M. N., Leroy, O., Mamede, A. S.
Format Journal Article
LanguageEnglish
Published Cham Springer International Publishing 01.04.2018
Springer
Springer Nature B.V
Springer Verlag
Subjects
Online AccessGet full text

Cover

Loading…
More Information
Summary:In the frame of severe accident topic for pressurized water reactor, the physical-chemistry of Ru fission products were experimentally studied to better understand their behavior inside the reactor coolant system in air or air/steam atmospheres. The tests consisted in vaporizing RuO 2 at 1200 °C and the ruthenium oxides are transported through a controlled thermal gradient tube made of quartz or pre-oxidized stainless steel. Results show that the major part up to 95% is deposited along the tube, the remaining part being transported almost under gaseous form attributed to RuO 4 . Impact of carrier gas, temperature profile and nature of the tube are discussed.
ISSN:0236-5731
1588-2780
DOI:10.1007/s10967-018-5743-2