Series: Nuclear and Reactor Constants

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

Authors & Affiliations

Zagorulko Yu.I., Vorobiova T.A.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia

Zagorulko Yu.I. – Cand. Sci. (Tech.), Leading Researcher, A.I. Leypunsky Institute for Physics and Power Engineering. Contacts: 1, pl. Bondarenko, Obninsk, Kaluga reg, Russia, 249033. Tel.: (484)399-80-84; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Vorobiova T.A. – Senior Researcher, A.I. Leypunsky Institute for Physics and Power Engineering.


To predict physicochemical behavior of carbon in fast reactors sodium coolant one needs a reliable correlation between thermodynamic activity and concentration of carbon in sodium solution. In previously made work this correlation was established by means of equilibrium tabs method for temperature range of 923-1023 K. It was desirable to extend temperature range to cover conditions being of interest for fast reactor technology application. In the article there are presented experimental results on the carbon activity/concentration correlation at sodium temperature of 823 and 873 K. In the experiments equilibrium tabs (Fe-11,6Mn; Fe-10Ni alloys) were used to measure carbon activity in high-temperature part of sodium circuit while carbon concentration was measured by means of chemical analysis of sodium samples taken in the circuit region close to equilibrium tabs position. It was shown experimentally that temperature and hydrodynamic conditions in the circuit provided complete dissolution of particulate carbon in high temperature region and its practically stationary concentration in the low temperature region. Activity coefficients for both values of temperature corresponded closely enough to inverse carbon terminal solubility in sodium.

fast reactor, sodium coolant, carbon, thermodynamic activity, particulate carbon, carbon concentration, diffusion-type carbon meter, equilibrium tabs, chemical analysis, sodium sampling, terminal solubility

Article Text (PDF, in Russian)


UDC 621.039.534.63

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2016, issue 4, 4:12