Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

Evaluation of coolant density history effect in RBMK type fuel modelling

  • Tonkunas, Aurimas (Lithuanian Energy Institute) ;
  • Pabarcius, Raimо (Lithuanian Energy Institute) ;
  • ndasSlavickas, Andrius (Lithuanian Energy Institute)
  • Received : 2019.11.24
  • Accepted : 2020.04.10
  • Published : 2020.11.25
Download PDF
⟨ Previous Next ⟩

Abstract

The axial heterogeneous void distribution in a fuel channel is a relevant and important issue during nuclear reactor analysis for LWR, especially for boiling water channel-type reactors. Variation of the coolant density in fuel channel has an effect on the neutron spectrum that will in turn have an impact on the values of absolute reactivity, the void reactivity coefficient, and the fuel isotopic compositions during irradiation. This effect is referring to as the history effect in light water reactor calculations. As the void reactivity effect is positive in RBMK type reactors, the underestimation of water density heterogeneity in 3D reactor core numerical calculations could cause an uncertainty during assessment of safe operation of nuclear reactor. Thus, this issue is analysed with different cross-section libraries which were generated with WIMS8 code at different reference water densities. The libraries were applied in single fuel model of the nodal code of QUABOX-CUBBOX/HYCA. The thermohydraulic part of HYCA allowed to simulate axial water distribution along fuel assembly model and to estimate water density history effect for RBMK type fuel.

Keywords

References

  1. Y. Maruyama, H. Asaka, A. Satou, H. Nakamura, Single rod experiments on transient void behavior during low-pressure reactivity-initiated accidents in light water reactors, Nucl. Eng. Des. 236 (2006) 1693-1700. https://doi.org/10.1016/j.nucengdes.2006.04.009
  2. Advanced Fuel Pellet Materials and Fuel Rod Design for Water Cooled Reactors vol. 1654, IAEA-TECDOC, 2010.
  3. K. Almenas, A. Kaliatka, E. Uspuras. Ignalina RBMK-1500. A Source Book. Extended and Updated Version, Lithuanian Energy Institute, Kaunas, Lithuania (1998).
  4. M. Fratoni, E. Greenspan, Neutronic design of hydride fueled BWRs, Nucl. Eng. Des. 239 (2009) 1531-1543. https://doi.org/10.1016/j.nucengdes.2009.01.016
  5. Nuclear Power Reactors in the world, 2018 edition), Reference Data Series No. 2, IAEA AEA-RDS-2/38.
  6. E. Uspuras, State of the art of the Ignalina RBMK-1500 safety, Sci. Technol. Nucl. Install. 2010 (2010) 11. https://doi.org/10.1155/2010/102078
  7. S. Langenbuch, W. Maurer, W. Werner, Coarse mesh flux expansion method for the analysis of space-time effects in large LWR cores, Nucl. Sci. Eng. 63 (1977) 437-456. https://doi.org/10.13182/NSE77-A27061
  8. S. Langenbuch, A. Petri, J. Steinborn, I.A. Stenbok, A.I. Suslow, Adaptation of GRS Calculation Codes for Soviet Reactors, Web, 1994.
  9. S. Langenbuch, W. Maurer, W. Werner, High-Order schemes for neutron kinetics calculation based on a local polynomial approximation, Nucl. Sci. Eng. 64 (1977) 508-516. https://doi.org/10.13182/NSE77-A27386
  10. R. Pabarcius, A. Tonkunas, E. Bubelis, M. Clemente, Uncertainty and sensitivity analysis of void and power reactivity coefficients in an RBMK-1500 reactor core, Kerntechnik. ISSN 70 (2005) 114-119, 0932-3902. https://doi.org/10.3139/124.100232
  11. W.I.M.S. The Answers Software Package, A Modular Scheme for Neutronics Calculations, in: User Guide for Version 8, ANSWERS/WIMS, 1999.
  12. M.J. Halsall, WIMS8 - Speed with Accuracy, ANS Topical Meeting, Long Island, USA, 1998.
  13. F. Jatuff, G. Perret, M.F. Murphy, F. Giust, R. Chawla, Void reactivity coefficient benchmark results for a 10x10 BWR assembly in the full 0-100% void fraction range, Ann. Nucl. Energy 36 (2009) 853-858. https://doi.org/10.1016/j.anucene.2009.02.013