The IFA-503.1 and −503.2 in-reactor experiments in the HBWR (Norway) are comparable to the microstructural studies of four types of VVER and PWR uranium dioxide fuel fabricated to standard specifications. On the basis of analysis, the radiation stability of VVER fuel as compared with PWR fuel isevaluated and a quantitative dependence of the effect of the initial submicron porosity on the thermoradiation densification of all experimental fuels is obtained. Data confirming a correlation between the radiation densification and a thermal test for dimensional stability are obtained for the fuels studied. Complex experimental studies made it possible to expand the database for verifying thermo-mechanical models and codes intended for predicting the behavior of high-burnup VVER.
Similar content being viewed by others
References
B. Yu. Volkov, E. P. Ryazantsev, V. V. Yakovlev, et al., “Investigation of the behavior of VVER and PWR fuel irradiated in the HBWR (Norway) reactor,” At. Énerg., 111, No. 6, 342–348 (2011).
B. Yu. Volkov, V. Visenak, E. P. Ryazantsev, et al., “Investigation of modified VVER fuel and standard PWR fuel in the HBWR reactor,” At. Énerg., 113, No. 3, 140–145 (2012).
B. Yu. Volkov, E. P. Ryazantsev, V. V. Yakovlev, et al., “Particulars of in-reactor behavior of in-reactor VVER and PWR uranium dioxide fuel with pellets of different shape,” At. Énerg., 113, No. 3, 139–144 (2013).
B. Volkov and T. Tverberg, “Irradiation performance of modified WWER fuel compared with typical PWR fuel in the Halden reactor test,” in: 4th Int. Conf. WWER Fuel Performance, Modeling and Experimental Support, Bulgaria, Oct. 1–5, 2001, pp. 186–196.
G. Small, “Densification of uranium dioxide at low burnup,” Nucl. Mater., 148, 302–315 (1987).
M. Freshley et al., “Irradiation-induced densification of UO2 pellet fuel,” Nucl. Mater., 62, 138–166 (1976).
D. V. Markov et al., “State of fuel rods spent in the VVER-1000 reactor up to a fuel burnup of 75 MW day/kgU,” in: 9th Int. Conf. WWER Fuel Performance, Modelling and Experimental Support, Bulgaria, Sept. 19–23, 2011, pp. 135–146.
R. Meyer, The Analysis of Fuel Densification, NUREG-0085 (1976).
A. Schubert, P. Uffelen, J. Laar, et al., “A feasibility test for improving the cladding behaviour predictions in WWER fuel rods with TRANSURANUS,” in: EHPG Meeting, Lillehammer, Oct. 2005, Session 4, Paper 7.
K. Vinjamuru and D. E. Owen, “Helium fill gas absorption in pressurised UO2 fuel rods during irradiation,” J. Nucl. Technol., 47, 119–124 (1980).
E. Underwood, Quantitative Stereology, Addison-Wesley Publishing Company, Inc., Philippines (1970).
V. Volkov, P. Strizhov, V. Yakovlev, et al., “Modelling of PWR and WWER fuel behaviour in Halden comparative tests using the new code SPAN,” in: IAEA-TECDOC-1233 (2002), pp. 305–321.
A. S. Shcheglov and V. N. Proselkov, “Software system for calculating the behavior of VVER fuel during operation under normal operating conditions: Program TOPRA,” in: 4th Int. Conf. Operating Experience, Modeling and Experimental Verification of VVER Fuel, Bulgaria, Oct. 1–5, 2001, pp. 220–228.
Author information
Authors and Affiliations
Additional information
Translated from Atomnaya Énergiya, Vol. 114, No. 6, pp. 325–331, June, 2013.
Rights and permissions
About this article
Cite this article
Volkov, B.Y., Jenssen, H., Ryazantsev, E.P. et al. Study of the Effect of Structural-Technological Parameters on the Thermo-Radiation Stability of VVER and PWR Fuel. At Energy 114, 404–411 (2013). https://doi.org/10.1007/s10512-013-9731-x
Received:
Published:
Issue Date:
DOI: https://doi.org/10.1007/s10512-013-9731-x