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Code improvement and model validation for Asco-II Nuclear Power Plant model using a coupled 3D neutron kinetics/thermal-hydraulic code

Autor
Pericas, R.; Ivanov, K.; Reventós, F.; Batet, L.
Tipus d'activitat
Article en revista
Revista
Annals of nuclear energy
Data de publicació
2016-01-01
Volum
87
Pàgina inicial
366
Pàgina final
374
DOI
https://doi.org/10.1016/j.anucene.2015.09.024 Obrir en finestra nova
Repositori
http://hdl.handle.net/2117/104075 Obrir en finestra nova
URL
http://www.sciencedirect.com/science/article/pii/S0306454915004685 Obrir en finestra nova
Resum
This paper provides a Best Estimate validation calculation with a coupled thermal–hydraulic and 3D neutron kinetic model for Ascó-II Nuclear Power Plant. Common NRC codes have been used for its purpose. TRACE is the code used for the thermal–hydraulic system calculations; PARCS is the code used for the 3D neutron kinetics calculations. Cross section calculations were performed with the HELIOS lattice physics code, finally GenPMAXS was used to convert the cross section into the PARCS format....
Citació
Pericas, R., Ivanov, K., Reventós, F., Batet, L. Code improvement and model validation for Asco-II Nuclear Power Plant model using a coupled 3D neutron kinetics/thermal-hydraulic code. "Annals of nuclear energy", 1 Gener 2016, vol. 87, p. 366-374.
Paraules clau
3D NK-TH, 3D neutron kinetics, Best Estimate calculation, Dynamic control rod movement, Nuclear safety, Reactor physics modeling
Grup de recerca
ANT - Advanced Nuclear Technologies Research Group

Participants