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RTOP-Code Simulation of the Radial Distribution of Heat Release and Plutonium Isotope Accumulation in High Burnup Oxide Fuel

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Abstract

A model of radial profiles of burnup, heat release, and accumulation of plutonium isotopes is described. The model was developed for use in the mechanistic RTOP fuel element code. The model is based on theoretical ideas about the mechanisms leading to the formation of the radial burnup profile and a simplified description of the neutron spectrum in the reactor, employing the idea of a hardness parameter. The hardness parameter gives the ratio of the thermal and superthermal parts of the neutron spectrum and is the only free input parameter of the model. The results, prsented in the paper, of a comparison of the predictions of the model with the experimental data show that the model possesses much better predictability than the currently most widely used module – TUBRNP.

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REFERENCES

  1. I. Palmer, K. Hesketh, and P. Jackson, “A model for predicting the radial power profile in a fuel pin,” in: Fuel Element Performance Computer Modeling, Report IWGFPT03, IAEA, Vienna (1982), Applied Science (1983), pp. 321–328.

    Google Scholar 

  2. K. Lassmann, C. O'Carroll. K. an de Laar, and C. Walker, “The radial distribution of plutonium in high burnup UO2 fuels,” J. Nucl. Materials, 208, 223–231 (1994).

    Google Scholar 

  3. D. Lanning, C. Beyer, and C. Painter, FRAPCON-3: Modifications to Fuel Rod Material Properties and Performance Models for High Burnup Application, NUREG/CR-6534, PNNL-11513, Vol. 1, October (1997).

  4. W. Wiesnack and T. Tverberg, “Thermal performance of high burnup fuel - in-pile temperature data and analysis,” in: Proceedings of the ANS Meeting Light Water Reactor Fuel Performance, Park City, Utah (2000), pp. 626–631.

  5. A. D. Galanin, Introduction to the Theory of Nuclear Reactors Operating on Thermal Neutrons, Énergoatomizdat, Moscow (1989), 2nd edition.

    Google Scholar 

  6. A. S. Shcheglov, V. D. Sidorenko, V. N. Proselkov, et al., “Formation and growth of a surface layer in VVÉR-440 fuel core,” At. Énerg., 80, No. 3, 221–223 (1996).

    Google Scholar 

  7. R. S. Grigor'ev and E. Z. Melikhov (eds.), Reference Data on Physical Quantities, Énergoatomizdat, Moscow (1991).

    Google Scholar 

  8. M. Kinoshita, T. Sonoda, S. Kitajima, et al., “High burnup RIM project (II). Irradiation and examination to investigate RIM-structured fuel,” in: Proceedings of the ANS Meeting Light Water Reactor Fuel Performance, Park City, Utah (2000), pp. 590–603.

  9. R. Manzel and C. Walker, “High burnup fuel microstructure and its effect on fuel performance,” ibid., pp. 604–614.

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Kurchatov, S.Y., Likhanskii, V.V., Sorokin, A.A. et al. RTOP-Code Simulation of the Radial Distribution of Heat Release and Plutonium Isotope Accumulation in High Burnup Oxide Fuel. Atomic Energy 92, 349–356 (2002). https://doi.org/10.1023/A:1016562228619

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  • DOI: https://doi.org/10.1023/A:1016562228619

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