Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear 2009
DOI: 10.1115/icone17-75661
|View full text |Cite
|
Sign up to set email alerts
|

Sensitivity Analysis by the Use of a Surrogate Model During Large Break LOCA on ZION Nuclear Power Plant With CATHARE-2 V2.5 Code

Abstract: In nuclear safety, the Best-Estimate (BE) codes may be used in demonstration and licensing, provided that uncertainties are added to the relevant output parameters before comparing them with the acceptance criteria. The uncertainty of output parameters, which comes mainly from the lack of knowledge of the input parameters, is evaluated by estimating the 95% percentile with a high degree of confidence. IRSN, technical support of the French Safety Authority, develop a method of uncertainty propagation and chose … Show more

Help me understand this report

Search citation statements

Order By: Relevance

Paper Sections

Select...
1

Citation Types

0
1
0

Year Published

2016
2016
2019
2019

Publication Types

Select...
2

Relationship

0
2

Authors

Journals

citations
Cited by 2 publications
(1 citation statement)
references
References 0 publications
0
1
0
Order By: Relevance
“…Within the frame of BEMUSE phase IV, IRSN used the CATHARE code as to build surrogate models for the analysis of Peak Cladding Temperature (PCT), one of the criteria of the LB-LOCA (Fouet et al, 2007). The approach is based on response surface methodology, constructed by Kriging.…”
Section: Introductionmentioning
confidence: 99%
“…Within the frame of BEMUSE phase IV, IRSN used the CATHARE code as to build surrogate models for the analysis of Peak Cladding Temperature (PCT), one of the criteria of the LB-LOCA (Fouet et al, 2007). The approach is based on response surface methodology, constructed by Kriging.…”
Section: Introductionmentioning
confidence: 99%