EDN: BLPCXE
Authors & Affiliations
Alekseev V.V., Sorokin A.P., Kuzina Yu.A.
A.I. Leypunsky Institute of Physics and Power Engineering, Obninsk, Russia
Alekseev V.V. – Chief Researcher, Dr. Sci. (Tech.). Contacts: 1, Bondarenko sq., Obninsk, Kaluga region, 249033. Tel.: +7 (484) 399-42-34; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Sorokin A.P. – Chief Researcher, Dr. Sci. (Tech.).
Kuzina Yu.A. – Director of Nuclear Energetic Department, Cand. Sci. (Tech.), A.I. Leypunsky Institute for Physics and Power Engineering.
Abstract
To select the performance and capacity of coolant purification systems, to develop requirements for impurity control
systems, it is necessary to assess the intensity of all potential sources of
impurities and predict their impact on the operation of installations during a
given resource. Quantitative estimates of impurities entering the coolant
(oxygen, hydrogen, carbon) during the preparatory and commissioning works,
including sodium supply, installation pollution, and the initial period of
operation, can be performed with sufficient reliability for practice. Due to
the increase in the intensity of impurity sources during NPP operation at rated
power with increased coolant parameters, more complete impurity control is
required. The tasks of operational control of these impurities are to maintain
acceptable levels of impurities in the coolant, timely detection of deviations
from the nominal operating regimes and prevention of emergency situations. To
control impurities in sodium coolant, a significant number of intermittent and
continuous devices based on various physical and chemical principles have been
developed. A description of a number of sodium impurity control devices used in
modern plants is given. Taking into account the state of
development of means for monitoring impurities in sodium coolant and shielding
gas, as well as the experience of using devices in reactor plants and
experimental stands, achieved in recent years, the necessary set of means for
monitoring impurities in sodium and gas cavity for their in-vessel placement
was determined in the tank of a promising sodium reactor.
Keywords
sodium coolant, impurities, control devices,
temperature, oxygen, hydrogen, corrosion products, shielding gas, cork
indicator, diffusion membrane
Article Text (PDF, in Russian)
References
1. Kozlov F.A., Volchkov L.G., Kuznetsov E.K.,
Matyukhin V.V. Zhidkometallicheskiye teplonositeli YAEU. Ochistka ot
primesey i ikh kontrol'. Pod red. d-ra tekhn. nauk Kozlova F.A.
[Liquid-metal coolants of nuclear power plants. Purification of impurities and
their control. Ed. Dr. Tech. Sciences Kozlov F.A.]. Enegoatomizdat, 1983. 128 p.
2. Alekseev V.V. Massoperenos tritiya i produktov
korrozii konstruktsionnykh materialov v konturakh s natriyevym teplonositelem.
Diss. dokt. tekhn. nauk [Mass transfer of tritium and corrosion products of
structural materials in circuits with sodium coolant. Dr. tech. sci. diss.].
Obninsk, IPPE, 2002.
3. OST 95 10582-2003. Standart otrasli. Natriy
reaktornoy chistoty dlya reaktorov BN. Tekhnicheskiye trebovaniya i metody
kontrolya primesey [OST 95 10582-2003. Industry
standard. Reactor-grade sodium for BN reactors. Technical requirements and
impurity control methods]. Obninsk, IPPE Publ., 2003.
4. Kozlov F.A., Poplavsky V.M., Alekseev V.V.,
Tsikunov A.G., Vorobieva T.A. Simulation of Tritium Mass Transfer in a
Three-Loop Sodium-Cooled Nuclear Power System. Atomic Energy, 2005, vol.
98, issue 3, pp. 163–169. Available at:
https://link.springer.com/article/10.1007/s10512-005-0187-5 (accessed
01.04.2022).
5. Ulmann H., Lang H.Yu., Kozlov F.A. et al.
Rezul'taty razrabotki elektrokhimicheskikh yacheyek dlya izmereniya aktivnosti
kisloroda v zhidkom natrii [Results of the development of electrochemical cells
for measuring the activity of oxygen in liquid sodium]. Preprint ZFK-565,
Dresden, 1985.
6. Zagorulko Yu.I., Kozub P.S., Sergeev G.P. Analiz
kontseptual'nogo vybora sistem obnaruzheniya protechek parogeneratorov
natriy-voda dlya reaktorov novogo pokoleniya [Analysis of the conceptual choice
of leak detection systems for sodium-water steam generators for new generation
reactors]. Preprint FEI-2719 – Preprint IPPE-2719, Obninsk, 1998.
7. Indikator vodoroda avtomaticheskiy IVA-1U. 0480.040.000 TU [Automatic hydrogen indicator IVA-1U]. Specification 0480.040.000.
8. Kozlov F.A., Egorov V.A., Kozub P.S. Operating
detectors for hydrogen in sodium on the BN-350
and BN-600 reactors. Atomic Energy, 1988, vol. 64, issue 3, pp. 287–290.
Available at: https://link.springer.com/article/10.1007/BF01123143 (accessed
01.04.2022).
9. Sergeev G.P., Kozub P.S. Primeneniye istochnika
impul'snogo napryazheniya dlya pitaniya magnitorazryadnogo nasosa indikatora
vodoroda [Application of a pulsed voltage source to power the magnetic
discharge pump of the hydrogen indicator]. Preprint FEI-2721 –
Preprint IPPE-2721. 1998.
10. Rettig D., Teske K., Ulmann H., Kozlov F.A., Zagorulko Yu.I. e.a.
Application of electrochemical cell to hydrogen detection in cover gas and to
carbon activity determination in sodium. Proc. Third Int. Conf. Liquid Metal
Engineering and Technology. Oxford, 1984. London: BNES, 1984, vol. 1, pp. 67–73.
11. Acher R.C., Horper D.C., Kirstein T.B.A. The Harwell Carbon Meter
(HCM). Proc. Second Int. Conf. on Liquid Metal Technology in Energy
Production. Richland, Washington, USA, April 20–24, 1980, CONF-800401.
12. McPheeters C.C. et al. Development and testing of a tritium meter
for sodium systems. Transactions ANS, 1977, vol. 27, no. 2, p. 287.
13. Carminati M., Hugla M., Morisson N.S., Trevillion E.A. et al.
Hydrogen and tritium behavior in Phenix and PFR. Proc. Fourth Int. Conf. on
Liquid Metal Engineering and Technology. Avignon, 1988, p. 620.
UDC 621.03921
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