Skip to main content
Log in

Development of a Computational Reactor Model in the IR Program Based on Experimental Data on Xenon Power Oscillations

  • Published:
Atomic Energy Aims and scope

A method of improving the computational reactor model in the IR program on the basis of the experimental data on the xenon power oscillations is presented. It is concluded on the basis of the deviation of the computed axial offset from experiment that the program requires adjustment. The program was modernized by replacing the dependence of the thermophysical parameters of the core on the specific rate of power release by solving the heat-conduction and heat-and-mass transfer equations. This is accomplished by means of the method and software used in the NOSTRA computer code, which were additionally improved by taking account of the influence of structural changes in the fuel on the thermal conductivity.

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

Access this article

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

Instant access to the full article PDF.

Similar content being viewed by others

References

  1. S. P. Aver’yanova, A. I. Kovel’, V. V. Mamichev, and P. E. Filimonov, “Development, adoption, and present status of the ‘Imitator reaktora’ software,” At. Énerg., 105, No. 4, 237–240 (2008).

    Google Scholar 

  2. D. M. Petrunin and V. I. Smenov, “Three-dimensional software – VVER reactor simulators,” Vopr. At. Nauki Tekhn. Ser. Fiz. Tekhn. Yad. Reakt., No. 9, 44–54 (1985).

  3. P. E. Filimonov and S. P. Aver’yanova, “Adjustment of the computational model for the instantaneous state of a reactor,” At. Énerg., 80, No. 6, 482–485 (1996).

    Article  Google Scholar 

  4. Yu. M. Semchenkov, V. A. Mil’to, B. E. Shumskii, and D. V. Vorob’eva, “Modernization of a diagnostics method for local boiling of the coolant in a VVER core,” At. Énerg., 118, No. 1, 6–10 (2015).

    Article  Google Scholar 

  5. S. G. Popov, V. K. Ivanov, J. Carbajo, and G. Yoder, Thermophysical Properties of MOX and UO 2 Fuels Including the Effects of Irradiation, ORNL/TM/351 (2000).

  6. P. Lucuta, Hj. Matzke, and R. Verrall, Modelling of UO 2 -Based SIMFUEL Thermal Conductivity the Effect of Burnup, Chalk River Lab. (1994).

  7. P. Lucuta, Hj. Matzke, and R. Verrall, “Characterization and thermal properties of hyperstoichiometric SIMFUEL,” 3rd Int. Conf. on CANDU Fuel, Canada (1992), pp. 2–61.

  8. P. Lucuta, Hj. Matzke, and I. Hastings, “A Pragmatic approach to modelling thermal conductivity of irradiated UO2 fuel: review and recommendations,” Nucl. Mater., No. 232, 166–180 (1996).

Download references

Author information

Authors and Affiliations

Authors

Additional information

Translated from Atomnaya Énergiya, Vol. 120, No. 1, pp. 9–12, January, 2016.

Rights and permissions

Reprints and permissions

About this article

Check for updates. Verify currency and authenticity via CrossMark

Cite this article

Aver’yanova, S.P., Vokhmyanina, N.S., Zlobin, D.A. et al. Development of a Computational Reactor Model in the IR Program Based on Experimental Data on Xenon Power Oscillations. At Energy 120, 10–14 (2016). https://doi.org/10.1007/s10512-016-0088-9

Download citation

  • Received:

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1007/s10512-016-0088-9

Keywords

Navigation