Safety analyses for nuclear power plants were carried out in the past using a conservative approach. With the increase of the phenomenological knowledge, through experimental data, and computational power, it became possible to adopt best estimate thermal- hydraulic system codes to perform deterministic safety analyses. However, some uncertainties are still present in the models, correlations, initial and boundary conditions, etc. Therefore, it is fundamental to quantify the uncertainty of calculation. This approach is called "Best Estimate Plus Uncertainty"(BEPU). Among the available uncertainty analysis methodologies, the probabilistic method to propagate input uncertainty is widely adopted. In the present study, an uncertainty analysis of a cold leg large break loss of coolant accident in a generic PWR-900 MWe has been developed and it has been carried out coupling the best estimate thermal- hydraulic system code TRACE and the uncertainty quantification tool DAKOTA in the SNAP environment/architecture.

Agnello G., Di Maio P.A., Bersano A., Mascari F. (2022). Cold Leg LBLOCA uncertainty analysis using TRACE/DAKOTA coupling. JOURNAL OF PHYSICS. CONFERENCE SERIES, 2177(1) [10.1088/1742-6596/2177/1/012023].

Cold Leg LBLOCA uncertainty analysis using TRACE/DAKOTA coupling

Agnello G.
;
Di Maio P. A.;
2022-04-13

Abstract

Safety analyses for nuclear power plants were carried out in the past using a conservative approach. With the increase of the phenomenological knowledge, through experimental data, and computational power, it became possible to adopt best estimate thermal- hydraulic system codes to perform deterministic safety analyses. However, some uncertainties are still present in the models, correlations, initial and boundary conditions, etc. Therefore, it is fundamental to quantify the uncertainty of calculation. This approach is called "Best Estimate Plus Uncertainty"(BEPU). Among the available uncertainty analysis methodologies, the probabilistic method to propagate input uncertainty is widely adopted. In the present study, an uncertainty analysis of a cold leg large break loss of coolant accident in a generic PWR-900 MWe has been developed and it has been carried out coupling the best estimate thermal- hydraulic system code TRACE and the uncertainty quantification tool DAKOTA in the SNAP environment/architecture.
13-apr-2022
Settore ING-IND/19 - Impianti Nucleari
Agnello G., Di Maio P.A., Bersano A., Mascari F. (2022). Cold Leg LBLOCA uncertainty analysis using TRACE/DAKOTA coupling. JOURNAL OF PHYSICS. CONFERENCE SERIES, 2177(1) [10.1088/1742-6596/2177/1/012023].
File in questo prodotto:
File Dimensione Formato  
RI-115 - Pre-print.pdf

accesso aperto

Tipologia: Pre-print
Dimensione 597.58 kB
Formato Adobe PDF
597.58 kB Adobe PDF Visualizza/Apri
Agnello_2022_J._Phys.__Conf._Ser._2177_012023.pdf

accesso aperto

Tipologia: Versione Editoriale
Dimensione 1.08 MB
Formato Adobe PDF
1.08 MB Adobe PDF Visualizza/Apri

I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.

Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/10447/579731
Citazioni
  • ???jsp.display-item.citation.pmc??? ND
  • Scopus 1
  • ???jsp.display-item.citation.isi??? ND
social impact