Abstract
The role of START-3 code in studying and computerized modelling of post-irradiation behaviour of standard fuel rods in real operation conditions of WWER-1000 reactors is described. The models used in the code are based on experimental study of material properties, processes and post irradiation research on standard and experimental fuel pins. The code capability is verified by comparison with data from experiments on WWER test rods performed in MR reactor, the Russia-Finland tests SOFIT and the international program FUMEX. The comparison performed and the results thus obtained demonstrate the satisfactory ability of START-3 code to simulate fuel rod behaviour in normal operation condition. The calculations confirm the experimentally observed evidence of an essential margin on serviceability of WWER-1000 fuel pin with three year operation cycle permitting an increase in design fuel burnup. 2 tabs., 18 figs.
Medvedev, A;
Bibilashvili, Yu;
Bogatyr, S;
Khvostov, G
[1]
- Vsesoyuznyj Nauchno-Issledovatel`skij Inst. Neorganicheskikh Materialov, Moscow (Russian Federation)
Citation Formats
Medvedev, A, Bibilashvili, Yu, Bogatyr, S, and Khvostov, G.
Modelling of WWER-1000 fuel: state and prospects.
Bulgaria: N. p.,
1994.
Web.
Medvedev, A, Bibilashvili, Yu, Bogatyr, S, & Khvostov, G.
Modelling of WWER-1000 fuel: state and prospects.
Bulgaria.
Medvedev, A, Bibilashvili, Yu, Bogatyr, S, and Khvostov, G.
1994.
"Modelling of WWER-1000 fuel: state and prospects."
Bulgaria.
@misc{etde_456091,
title = {Modelling of WWER-1000 fuel: state and prospects}
author = {Medvedev, A, Bibilashvili, Yu, Bogatyr, S, and Khvostov, G}
abstractNote = {The role of START-3 code in studying and computerized modelling of post-irradiation behaviour of standard fuel rods in real operation conditions of WWER-1000 reactors is described. The models used in the code are based on experimental study of material properties, processes and post irradiation research on standard and experimental fuel pins. The code capability is verified by comparison with data from experiments on WWER test rods performed in MR reactor, the Russia-Finland tests SOFIT and the international program FUMEX. The comparison performed and the results thus obtained demonstrate the satisfactory ability of START-3 code to simulate fuel rod behaviour in normal operation condition. The calculations confirm the experimentally observed evidence of an essential margin on serviceability of WWER-1000 fuel pin with three year operation cycle permitting an increase in design fuel burnup. 2 tabs., 18 figs.}
place = {Bulgaria}
year = {1994}
month = {Dec}
}
title = {Modelling of WWER-1000 fuel: state and prospects}
author = {Medvedev, A, Bibilashvili, Yu, Bogatyr, S, and Khvostov, G}
abstractNote = {The role of START-3 code in studying and computerized modelling of post-irradiation behaviour of standard fuel rods in real operation conditions of WWER-1000 reactors is described. The models used in the code are based on experimental study of material properties, processes and post irradiation research on standard and experimental fuel pins. The code capability is verified by comparison with data from experiments on WWER test rods performed in MR reactor, the Russia-Finland tests SOFIT and the international program FUMEX. The comparison performed and the results thus obtained demonstrate the satisfactory ability of START-3 code to simulate fuel rod behaviour in normal operation condition. The calculations confirm the experimentally observed evidence of an essential margin on serviceability of WWER-1000 fuel pin with three year operation cycle permitting an increase in design fuel burnup. 2 tabs., 18 figs.}
place = {Bulgaria}
year = {1994}
month = {Dec}
}