Skip to main content
SpringerLink
Log in

A model for calculating composition and density of the core melt in the water-moderated water-cooled reactor in case of severe accident

  • Published:
Thermal Engineering Aims and scope Submit manuscript

Abstract

Thermochemical behavior of the core melt in the VVER-type reactor at severe accident is discussed. Experimental information gained made it possible to construct a thermodynamic model of the O-U-Zr-Fe system. The model describes the immiscibility of the oxide and metal phases of the core melt and makes it possible to estimate their densities. Parameters of the model were obtained by comparison with diagrams of binary and ternary subsystems, as well as with results of the MASCA experiment. Additional verification calculations show good agreement of the theory with experiment. In particular, parametric calculations showed that there is a wide enough region of the core melt parameters at which densities of the oxide and metal phases are comparable in values, but this fact does not rule out the probability of stratification with upper position of the oxide layer. In its simplified formulation the model has been incorporated into the HEFEST code. Results are reported for calculations of heat transfer in the stratified core melt in the reactor vessel for two different cases of relative location of the melt layers.

This is a preview of subscription content, log in via an institution to check access.

Access this article

Log in via an institution

Price excludes VAT (USA)
Tax calculation will be finalised during checkout.

Instant access to the full article PDF.

Institutional subscriptions

Similar content being viewed by others

References

  1. G. Gueneau, M. Baichi, L. Labroche, et al., “Thermodynamic Assessment of the Uranium-Oxygen System,” J. Nucl. Mater. 304, 161 (2002).

    Article  Google Scholar 

  2. P. Y. Chevallier, E. Fischer, and B. Cheynet, “Progress in the Thermodynamic Modeling of the O-U Binary System,” J. Nucl. Mater. 303, 1 (2002).

    Article  Google Scholar 

  3. B. Cheynet, P. Chaud, P. Y. Chevallier, et al., “THER-MODATA DOCUMENTATION” (2005).

  4. P. Y. Chevallier and E. Fischer, “Thermodynamic Modeling of the of the O-U-Zr System,“ J. Nucl. Mater. 257, 213 (1998).

    Article  Google Scholar 

  5. RASLPAV Application Report, QESD RASPLAV SEMINAR, Munich, 2000.

  6. Main Results of the First Phase of MASCA Project. Integrated Report (2004).

  7. V. G. Asmolov, V. N. Zagryazkin, and D. F. Tsurikov, “Thermodynamics of the U-Zr-Fe-O Melts,” TVT 45(3), 347 (2007).

    Google Scholar 

  8. O. Redlich and A. Kister, Ind. Eng. Chem. 40, 345 (1948).

    Article  Google Scholar 

  9. V. G. Asmolov, V. Yu. Vishnevskii, Ye. K. Dyakov, et al., “Study of the Processes of Interaction in the Reactor of the VVER Type in Case of a Severe Accident. Interaction between Melts of the Oxide Corium and Steel,” Preprint IAE-6423 (Moscow, Institute of Atomic Energy, 2006).

    Google Scholar 

  10. V. F. Strizhov et. al. “Development of a Database for Thermophysical Properties of Corium: Pure Components”, in Report on the Project. Task 1.1 (2006).

  11. M. I. Shakhparonov, Introduction into Molecular Theory of Solutions (Moscow, GITTL, 1956) [in Russian].

    Google Scholar 

  12. V. G. Asmolov, V. N. Zagryazkin, and D. F. Tsurikov, “Estimate of the Density of the U-Zr-Fe-O Melts,” TVT. 46(4), 635 (2008).

    Google Scholar 

  13. A. S. Filippov, N. A. Nosunova, and V. F. Strizhov, “Simulation of the Core Melt in the Vessel of the VVER Reactor in the SOCRAT/HEFEST Code,” Izv. RAN, Energetika, No. 3 (2010).

  14. A. S. Filippov, N. I. Drobyshevskii, A. Ye. Kiselev et al., “SOCRAT/HEFEST: Models of Interaction between Melt of the Core of the VVER Reactor and Structures at a Severe Accident,” Izv. RAN, Energetika.

  15. V. V. Gusarov, V. B. Khabenskii, S. V. Beshta, et. al., Sacrifcial Material Used in the Core Melt Localization Device at Beyond-to-Design Basis Accidents at Nuclear Plants Equipper with the VVER-1000 Reactor: Concept of Development, Justification and Inmplementation,” in Problems of Safety of NPP with VVER Reactors, Scientific and Practical Seminar, Saint-Petersburg, September 12–14, 2000.

  16. A. Filippov, V. Strizhov, and O. Tarasov, “Application of MASCA Results to Analysis of Severe Accident Scenarios,” MASCA2 Seminar, Cadarasche, France, October 11–12, 2007.

Download references

Authors
  1. V. D. Ozrin
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. O. V. Tarasov
    View author publications

    You can also search for this author in PubMed Google Scholar

  3. V. F. Strizhov
    View author publications

    You can also search for this author in PubMed Google Scholar

  4. A. S. Filippov
    View author publications

    You can also search for this author in PubMed Google Scholar

Additional information

Original Russian Text © V.D. Ozrin, O.V. Tarasov, V.F. Strizhov, A.S. Filippov, 2010, published in Izvestiya RAN. Energetika.

Rights and permissions

Reprints and permissions

About this article

Cite this article

Ozrin, V.D., Tarasov, O.V., Strizhov, V.F. et al. A model for calculating composition and density of the core melt in the water-moderated water-cooled reactor in case of severe accident. Therm. Eng. 57, 1099–1111 (2010). https://doi.org/10.1134/S0040601510130033

Download citation

  • Received:

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1134/S0040601510130033

Keywords

Search

Navigation