PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY
Series: Nuclear and Reactor Constants

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

STUDY OF THE EFFECTIVENESS OF LITHIUM HYDROXIDE USING FOR HIGH TEMPERATURE pHT CONTROL AT THE SUPERCRITICAL COOLANT

EDN: EEZIMU

Authors & Affiliations

Kharitonova N.L.
National Research Nuclear University Moscow Engineering Physics Institute, Moscow, Russia

Kharitonova N.L. – Leading Researcher, Cand. Sci. (Tech.). Contacts: 31, Kashirskoe shosse, Moscow, 115409. Tel.: +7 (499) 324-77-77; е-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..

Abstract

The article is devoted to the calculation of the high-temperature pHt in aqueous solutions of lithium hydroxide under conditions of supercritical parameters of pressure and temperature. The concept of maintaining the water-chemical regime of the primary coolant of “classical” VVER/PWR power units involves operating in alkaline conditions by dosing potassium/lithium hydroxide depending on changes in the concentration of boric acid in order to minimize corrosion and the transfer of corrosion products. Using the example of lithium hydroxide (LiOH), the article examines the possibility of properly regulating the acid-base properties of the coolant by dosing alkali in near- and supercritical regions for VVER-SCP nuclear power plants. The pHT values of dilute aqueous solutions of LiOHaq are calculated at a pressure of 25 MPa depending on the density of H2O in the temperature range from 100 to 600 °C, and LiOHaq concentrations from 10–6 to 1–3 mol/kg. For these conditions, the degree of LiOHaq dissociation was also calculated depending on the H2O density. The values of the dissociation constant of LiOHaq at elevated temperatures and pressures are taken based on an analysis of published experimental and evaluated calculation data. It was found that at a H2O density below 80 kg/m3 (temperature above 540 °C at 25 MPa) for LiOHaq concentrations from 10–6 to 10–3 mol/kg, the pHT values in the LiOH–H20 system and in pure H2O are practically the same, and LiOHaq is almost completely in an associated state. Therefore, under these conditions, due to weak dissociation of LiOHaq, pHT control is practically impossible. Dosing LiOH into the coolant will ensure the pHt control at temperatures below ≈ 400 °C for 25 MPa. The results obtained are in good agreement with the conclusions of previously published work.

Keywords
supercritical water cooled reactor, safety, water coolant, VVER-SCP, high-temperature hydrogen index pHt, ion product of water, water chemistry, lithium hydroxide, concentration, experimental data, electrolytic dissociation, physical and chemical properties of water coolant

Article Text (PDF, in Russian)

References

  1. Asmolov V.G. Perspektivy razvitiya tekhnologii VVER v dvukhkomponentnoy YaES Rossii [Prospects for the Development of VVER Technology]. V sb.: Sbornik dokladov VI Mezhdunarodnoy nauchno-tekhnicheskoy konferentsii “Innovatsionnyye proyekty i tekhnologii yadernoy energetiki” [Proc. of the VI International Scientific and Technical Conference “Innovative Projects and Technologies of Nuclear Power”. Moscow, November 14–17, 2023, paper P-2. Available at: https://istc-2023.nikiet.ru/file/dis-ru/1/П-2.pdf (accessed 28.04.2024).
  2. High Temperature On-line Monitoring of Water Chemistry and Corrosion Control in Water Cooled Power Reactor. IAEA-TECDOC-1303, IAEA, Vienna, 2002.
  3. Pressurized Water Reactor Primary Water Chemistry Guidelines, Volumes 1 and 2, Revision 7. EPRI, Palo Alto, CA: 2014. 3002000505.
  4. Fruzzetti K., Marks C., Reinders J., McElrath J., Wells D.M. Evaluation of Potassium Hydroxide for Reactor Coolant pHT Control in Western PWRs. Proc. of the 20th NPC International Conference. Brighton, United Kingdom, 2016, October 2–7, Paper Number 06.
  5. STO 1.1.1.02.005.0004-2012. Vodno-khimicheskiy rezhim pervogo kontura energoblokov atomnykh elektrostantsiy s reaktorami VVER-1000. Normy kachestva teplonositelya i sredstva ikh obespecheniya [Primary Water Chemistry of Power Units of Nuclear Power Plants with VVER-1000 Reactors. Coolant Quality Standards and Means of Ensuring Them]. Moscow, Rosenergoatom Publ., 2012.
  6. Sharafutdinov R.B., Kharitonova N.L. The problem of optimizing the water chemistry used in the primary coolant circuit of a nuclear power station equipped with VVER reactors under the conditions of
    longer fuel cycle campaigns and increased capacity of power units. Therm. Eng., 2011, vol. 58, issue 5, pp. 383–389. DOI: https://doi.org/10.1134/S0040601511050120.
  7. Martynova O.I., Kharitonova N.L. Behavior of Lithium Metaborates in Solution in Steam Generators under Conditions of Intensive Evaporation. Thermal Engineering, 1990, vol. 37, no. 10, рр. 536–540.
  8. Helgeson H.C., Kirkham D.H., Flowers G.C. Theoretical prediction of the thermodynamic behavior of aqueous electrolytes by high pressures and temperatures; IV, calculation of activity coefficients, osmotic coefficients, and apparent molal and standard and relative partial molal properties to 600 degrees C and 5 kb. American Journal of Science, 1981, vol. 281, no. 10, pp. 1249–1516.
  9. International Association for the Properties of Water and Steam. IAPWS R11-07(2019). Revised Release on the Ionization Constant of H2O. 2019. Available at: http://www.iapws.org/relguide/Ionization.pdf (accessed 24.07.2024).
  10. Arcis H., Ferguson J.P., Cox J.S., Tremaine P.R. The Ionization Constant of Water at Elevated Temperatures and Pressures: New Data from Direct Conductivity Measurements and Revised Formulations from T = 273 K to 674 K and p = 0.1 MPa to 31 MPa. J. Phys. Chem. Ref. Data, 2020, vol. 49, pр. 03310–31―03310–37. DOI: 10.1063/1.5127662.
  11. Yoshida N., Matsugami M., Harano Y., Nishikawa K., Hirata F. Structure and Properties of Supercritical Water: Experimental and Theoretical Characterizations, 2021, vol. 4, pp. 698–726. DOI: https://doi.org/10.3390/j4040049.
  12. Kharitonova N.L., Gurbanova Sh.A. Termodinamicheskie dannye dlya rascheta vysokotemperaturnogo vodorodnogo pokazatelya pHT vodnogo teplonositelya reaktornyh ustanovok sverhkriticheskih parametrov [Thermodynamic Data for the Calculation of the High-Temperature pHt of the Water Coolant in Reactor Units with Supercritical Parameters]. Voprosy atomnoy nauki i tekhniki. Seriya: Yaderno-reaktornyye konstanty – Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2022, no. 4, pp. 201–213. Available at: https://vant.ippe.ru/images/pdf/2022/issue2022-4-201-213.pdf (accessed 28.03.2024).
  13. Helgeson H.C., Kirkham D.H. Theoretical prediction of the thermodynamic properties of aqueous electrolytes at high pressures and temperatures. III. Equation of state for aqueous species at infinite dilution. American Journal of Science, 1976, vol. 276, no. 2, pp. 97–240.
  14. Helgeson C., Kirkham D.H. Theoretical prediction of the thermodynamic behavior of aqueous electrolytes at high pressures and temperatures; II, Debye-Huckel parameters for activity coefficients and relative partial molal properties. American Journal of Science, 1974, vol. 274, no. 10, pp. 1199–1261.
  15. Corti H., Crovetto R., Fernández-Prini R. Aqueous Solutions of Lithium Hydroxide at Various Temperatures: Conductivity and Activity Coefficients. Journal of Solution Chemistry, 1979, vol. 8, no. 12, pp. 897–908. DOI: 10.1007/bf00644886.
  16. Ho P.C., Palmer D.A. Determination of ion association in dilute aqueous lithium chloride and lithium hydroxide solutions to 600 °C and 300 MPa by electrical conductance measurements. Journal of Chemical and Engineering Data. 1998, vol. 43, no. 2, pp. 162–170.
  17. Ho P.C., Palmer D.A., Wood R.H. Conductivity measurements of dilute aqueous LiOH, NaOH and KOH solutions to high temperatures and pressures using a flow-through cell. Journal of Physical Chemistry B, 2000, vol. 104, no. 50, pp. 12084–12089.
  18. Ho P.C., Bianchi H., Palmer D.A., Wood R.H. Conductivity of dilute aqueous electrolyte solutions at high temperatures and pressures using a flow cell. Journal of Solution Chemistry, 2000, vol. 29, no. 2, pp. 217–235.
  19. Shcherbakov V.N., Lukashov Yu.Yu., Lukashov Yu.M. Electrolytical properties of solutions of lithium hydroxide at high temperatures and pressures. Therm. Eng., 2013, vol. 60, issue 4, pp. 280–284. DOI: https://doi.org/10.1134/S0040601513040125.
  20. Akinfiev N. Thermodynamic description of alkali metal hydroxides over a wide range of temperatures, pressures and densities of aqueous. Proc. of the 16th International Symposium on Water-Rock Interaction (WRI-16) and 13th International Symposium on Applied Isotope Geochemistry (1st IAGC International Conference). E3S Web Conf. Volume 98, 2019. DOI: https://doi.org/10.1051/e3sconf/20199805001.
  21. Plugatyr A., Carvajal-Ortiz R.A., Svishchev I.M. Ion-pair association constant for LiOH in supercritical water. J. Chem. Eng. Data, 2011, vol. 56(9), pp. 3637–3642. DOI: 10.1021/je2004808.
  22. Carvajal-Ortiz R.A., Plugatyr A., Svishchev I.M. On the pH Control at the Supercritical Water-cooled Reactor Operating Conditions. Nuclear Eng. and Design, 2012, vol. 248, pp. 340–342. DOI: 10.1016/j.nucengdes.2012.03.038.
  23. Revised Release on the IAPWS Industrial Formulation 1997 for the Thermodynamic Properties of Water and Steam. International Association for the Properties of Water and Steam. s.l.: IAPWS, 2007. Available at: http://www.iapws.org/relguide/IAPWS-95.html (accessed 30.03.2024).
  24. Svishchev I.M., Carvajal-Ortiz R.A., Choudhry K.I. Supercritical water, hydrogen production and ion association in nuclear power cycles. Proc. of the 16th International Conference on the Properties of Water and Steam. London, United Kingdom, 2013, September 1–5. Available at: https://www.researchgate.net/profile/Kashif-Choudhry-2/publication/259912260_Supercritical_water_hydrogen_production_and_ion_association_in_nuclear_power_cycles/links/0a85e52e8344da6b48000000/Supercritical-water-hydrogen-production-and-ion-association-in-nuclear-power-cycles.pdf (accessed 27.07.2024).
  25. Svishchev I.M., Carvajal-Ortiz R.A., Choudhry K.I., Guzonas D.A. Corrosion behavior of stainless steel 316 in sub- and supercritical aqueous environments: effect of LiOH additions. Corrosion Science, 2013, vol. 72, pp. 20–25.
  26. Guzonas D.A., Tremaine P., Brosseau F., Meesungnoen J., Jay-Gerin J.-P. Key water chemistry issues in a supercritical-water-cooled pressure-tube reactor. Nuclear Technology, 2012, vol. 179, p. 205.

UDC 621.039.58

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2024, no. 3, 3:12