Abstract
Thermal-physical characteristics of fuel rods of two fuel assemblies which were operated within 5 - 8 and 5 - 9 core fuel loadings of the Unit 3 of the Kol`skaya NPP are calculated. They have achieved deep burnup during 4-year (> 46 Mwd/kg U) and 5-year (> 48 Mwd/kg U) fuel cycle. Fuel assemblies have been unloaded off the reactor and subjected to a post-irradiation testing. PIN-mod2 code originally designed for modelling of WWER fuel rod behaviour in a quasi-steady-state operation is used. The average fuel rod in the fuel assembly and the fuel rod with maximum burnup are selected. The preliminary comparison of the calculation results with those of the post-irradiation examination shows a satisfactory agreement. On the basis of the results obtained in the post-irradiation experiments an improvement of the model for calculation of fission gas release and creep of the cladding is planned. The results of the analysis performed indicate that the fuel rod completely preserves its working ability; fuel temperature does not exceed 1300{sup o} C; fission gas release does not exceed 4%; maximum gas pressure inside the cladding at the end of campaign does not exceed 2 MPa. 2 tabs., 11 figs., 5 refs.
Scheglov, A;
Proselkov, V;
[1]
Panin, M;
Pitkin, Yu;
[2]
Tzibulya, V
[3]
- Russian Research Centre Kurchatov Inst., Moscow (Russian Federation)
- Kol`skaya NPP, (Russian Federation)
- AO Mashinostroitelnij Zavod Electrostal (Russian Federation)
Citation Formats
Scheglov, A, Proselkov, V, Panin, M, Pitkin, Yu, and Tzibulya, V.
Results of calculation of WWER-440 fuel rods (Kol`skaya-3 NPP) at high burnup.
Bulgaria: N. p.,
1994.
Web.
Scheglov, A, Proselkov, V, Panin, M, Pitkin, Yu, & Tzibulya, V.
Results of calculation of WWER-440 fuel rods (Kol`skaya-3 NPP) at high burnup.
Bulgaria.
Scheglov, A, Proselkov, V, Panin, M, Pitkin, Yu, and Tzibulya, V.
1994.
"Results of calculation of WWER-440 fuel rods (Kol`skaya-3 NPP) at high burnup."
Bulgaria.
@misc{etde_456086,
title = {Results of calculation of WWER-440 fuel rods (Kol`skaya-3 NPP) at high burnup}
author = {Scheglov, A, Proselkov, V, Panin, M, Pitkin, Yu, and Tzibulya, V}
abstractNote = {Thermal-physical characteristics of fuel rods of two fuel assemblies which were operated within 5 - 8 and 5 - 9 core fuel loadings of the Unit 3 of the Kol`skaya NPP are calculated. They have achieved deep burnup during 4-year (> 46 Mwd/kg U) and 5-year (> 48 Mwd/kg U) fuel cycle. Fuel assemblies have been unloaded off the reactor and subjected to a post-irradiation testing. PIN-mod2 code originally designed for modelling of WWER fuel rod behaviour in a quasi-steady-state operation is used. The average fuel rod in the fuel assembly and the fuel rod with maximum burnup are selected. The preliminary comparison of the calculation results with those of the post-irradiation examination shows a satisfactory agreement. On the basis of the results obtained in the post-irradiation experiments an improvement of the model for calculation of fission gas release and creep of the cladding is planned. The results of the analysis performed indicate that the fuel rod completely preserves its working ability; fuel temperature does not exceed 1300{sup o} C; fission gas release does not exceed 4%; maximum gas pressure inside the cladding at the end of campaign does not exceed 2 MPa. 2 tabs., 11 figs., 5 refs.}
place = {Bulgaria}
year = {1994}
month = {Dec}
}
title = {Results of calculation of WWER-440 fuel rods (Kol`skaya-3 NPP) at high burnup}
author = {Scheglov, A, Proselkov, V, Panin, M, Pitkin, Yu, and Tzibulya, V}
abstractNote = {Thermal-physical characteristics of fuel rods of two fuel assemblies which were operated within 5 - 8 and 5 - 9 core fuel loadings of the Unit 3 of the Kol`skaya NPP are calculated. They have achieved deep burnup during 4-year (> 46 Mwd/kg U) and 5-year (> 48 Mwd/kg U) fuel cycle. Fuel assemblies have been unloaded off the reactor and subjected to a post-irradiation testing. PIN-mod2 code originally designed for modelling of WWER fuel rod behaviour in a quasi-steady-state operation is used. The average fuel rod in the fuel assembly and the fuel rod with maximum burnup are selected. The preliminary comparison of the calculation results with those of the post-irradiation examination shows a satisfactory agreement. On the basis of the results obtained in the post-irradiation experiments an improvement of the model for calculation of fission gas release and creep of the cladding is planned. The results of the analysis performed indicate that the fuel rod completely preserves its working ability; fuel temperature does not exceed 1300{sup o} C; fission gas release does not exceed 4%; maximum gas pressure inside the cladding at the end of campaign does not exceed 2 MPa. 2 tabs., 11 figs., 5 refs.}
place = {Bulgaria}
year = {1994}
month = {Dec}
}