Abstract
The purpose of this paper is the assessment of the FA pin-by-pin model available in the KORSAR/GP code. The paper presents the results of the simulation of an “Control rod ejection” accident. This accident is of interest due to the power redistribution in the FAs effected by the ejection. The safety margins are calculated with the use of the “hot channel” model for NPP safety analyses. Only the fuel rods of the core with the highest power are taking into account. The absence of the change of the pin power distribution for the FA during the transient is compensated by increased conservatism. In this paper, the maximum fuel rod power was obtained using the pin-by-pin model.
Kurzfassung
Dieser Beitrag präsentiert eine Bewertung des Brennelement-Pin-by-Pin-Modells des Programms KORSAR/GP anhand einer Berechnung des Szenarios Steuerstabauswurf. Dieses Szenario ist aufgrund der durch den Auswurf verursachten Energieumverteilung in den Brennelementen von Interesse. Die Sicherheitsmargen werden mit Hilfe des „Heißkanal“-Modells für die Sicherheitsanalysen von Kernkraftwerken berechnet. Es werden nur die Brennstäbe des Kerns mit der höchsten Leistung berücksichtigt. Das Fehlen einer Änderung der Pin-Leistungsverteilung für das Brennelement während der Transienten wird durch erhöhten Konservatismus kompensiert. In diesem Beitrag wurde die maximale Brennstableistung mit dem Pin-by-Pin-Modell ermittelt.
References
1 Gordienko, P. V.: Transient neutron-physics simulation using pin-by-pin nodalization for VVER NPP. Dissertation abstract for the candidate of engineering sciences degree Moscow, 2014Search in Google Scholar
2 Gordienko, P. V; Kotsarev, A. V.; Lisorkin, M. P.: The method of pin-by-pin energy reconstruction in code BIPR-8 for VVER reactor. Moscow, 2012Search in Google Scholar
3 AwakumowA.; MalofeewV.: Validation of an advanced heterogeneous model for LWR detailed pin-by-pin calculations. International conference on the physics of nuclear science and technology, 1998Search in Google Scholar
4 Panka, I.; Hegyi, Gy.; Kereszturi, A.; Maraczy, Cs.; Temesvari, E.: Hot channel calculation methodologies in case of VVER-1000/1200 reactors. Kerntechnik83 (2018) 365–37510.3139/124.110899Search in Google Scholar
5 Bykov, M. A.; Lisenkov, E. A.; Bezrukov, Yu. A.; Moskalev, A. M.; Alekhin, G. V.; Beliaev, U. V.; Zaitsev, S. I.; Zakutaev, M. O.; Kurbaev, S. A.: Modelling of coolant mixing processes in reactor by codes TRAP-KC, DKM and KORSAR. Proceedings of the 6th International Conference “Safety Assurance of NPP with VVER”, Russia, Moscow region, Podolsk, May 26–29, 2009Search in Google Scholar
6 Artemov, V. G.; Artemova, L. M.; Korotaev, V. G.; Mikheev, P. A.; Shemaev, U. P.: The combined method for pin-to-pin power density calculation with the SAPFIR_95&RC_VVER software package. 24th Symposium of AER on VVER Reactor Physics and Reactor Safety, Russia, Sochi, 2014Search in Google Scholar
7 Sinegribova, A. I.; Petkevich, I. G.: Development of the fuel assembly pin-by-pin model in the code KORSAR/GP. Proceedings of the 10th International Conference “Safety Assurance of NPP with WWER. Russia, Moscow region, Podolsk, 2017Search in Google Scholar
8 Sinegribova, A. I.; Uvakin, M. A.: Application of fuel assembly pin-by-pin model developed by code KORSAR/GP for VVER NPP transient simulation. Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 4 (2017) (in Russian)Search in Google Scholar
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