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Failure identification in a nuclear passive safety system by Monte Carlo simulation with adaptive Kriging
- Source :
- Nuclear Engineering and Design, Nuclear Engineering and Design, Elsevier, 2021, 380, pp.111308. ⟨10.1016/j.nucengdes.2021.111308⟩
- Publication Year :
- 2021
- Publisher :
- HAL CCSD, 2021.
-
Abstract
- Passive Safety Systems (PSSs) are increasingly employed in advanced Nuclear Power Plants (NPPs). Their safety performance is evaluated through computationally expensive Thermal-Hydraulic (T-H) simulations models and the identification of the operational conditions which lead to unsafe conditions (the so-called Critical failure Regions, CRs) may be challenging. In the present paper, a computational framework is proposed to identify the CRs of a generic passive Decay Heat Removal (DHR) system of a NPP. A time-demanding Best-Estimate Thermal-Hydraulic (BE-TH) model of the system is used to train a fast-running metamodel embedded within an adaptive sampling technique of literature, namely Adaptive Kriging Monte Carlo Sampling (AK-MCS), so as to provide increased accuracy in proximity of the failure threshold and identify which input values lead the PSS to failure. To the best authors’ knowledge this is the first time that the metamodel-based AK-MCS technique is applied for the identification of the CRs of a PSS of an NPP.
- Subjects :
- Nuclear and High Energy Physics
Adaptive sampling
Computer science
020209 energy
Monte Carlo method
System safety
02 engineering and technology
01 natural sciences
Critical failure region
010305 fluids & plasmas
law.invention
Adaptive-Kriging Monte Carlo Sampling (AK-MCS)
law
Kriging
0103 physical sciences
Nuclear power plant
0202 electrical engineering, electronic engineering, information engineering
Adaptive-Kriging Monte Carlo Sampling
General Materials Science
Passive safety system
Decay heat
[SHS.GEST-RISQ]Humanities and Social Sciences/domain_shs.gest-risq
Safety, Risk, Reliability and Quality
Waste Management and Disposal
ComputingMilieux_MISCELLANEOUS
Mechanical Engineering
Decay heat removal
Reliability engineering
Metamodeling
Identification (information)
Nuclear Energy and Engineering
Subjects
Details
- Language :
- English
- ISSN :
- 00295493
- Database :
- OpenAIRE
- Journal :
- Nuclear Engineering and Design, Nuclear Engineering and Design, Elsevier, 2021, 380, pp.111308. ⟨10.1016/j.nucengdes.2021.111308⟩
- Accession number :
- edsair.doi.dedup.....c263f6faf98cf649de69a77980c693a3
- Full Text :
- https://doi.org/10.1016/j.nucengdes.2021.111308⟩