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Uncertainties in pressurized thermal shock analyses
Niffenegger M; Garrido OC; Mora DF; Qian GA(钱桂安); Mukin R; Sharabi M; Lafferty N; Niceno B
Source PublicationAmerican Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP
Conference NameASME 2019 Pressure Vessels and Piping Conference, PVP 2019
Conference DateJuly 14, 2019 - July 19, 2019
Conference PlaceSan Antonio, TX, United states
AbstractIntegrity assessment of reactor pressure vessels (RPVs) can be performed either by deterministic fracture mechanics (DFM) or/and by probabilistic fracture mechanics (PFM) analyses. In European countries and Switzerland, only DFM analyses are required. However, in order to establish the probabilistic approach in Switzerland, the advantages and shortcomings of the PFM are investigated in the frame of a national research project. Both, the results from DFM and PFM depend strongly on the previous calculated thermal-hydraulic boundary conditions. Therefore, complete integrity analyses involving several integrated numerical codes and methods were performed for a reference pressurized water reactor (PWR) RPV subjected to pressurized thermal shock (PTS) loads. System analyses were performed with the numerical codes RELAP5 and TRACE, whereas for structural and fracture mechanics calculations, the FAVOR and ABAQUS codes were applied. Additional computational fluid dynamics analyses were carried out with ANSYS/FLUENT, and the plume cooling effect was alternatively considered with GRS-MIX. The results from the different analyses tools are compared, to judge the expected overall uncertainty and reliability of PTS safety assessments. It is shown that the scatter band of the stress intensities for a fixed crack configuration is rather significant, meaning that corresponding safety margins should be foreseen. The conditional probabilities of crack initiation and RPV failure might also differ, depending on the considered random parameters and applied rules. Copyright © 2019 ASME.
KeywordComputational fluid dynamics Finite element method Pressurized thermal shock Probabilistic fracture mechanics Warm pre-stressing
Indexed ByEI
Document Type会议论文
Affiliation1.Paul Scherrer Institut, Nuclear Energy and Safety Department, Villigen PSI, CH-5232, Switzerland
2.State Key Laboratory of Nonlinear Mechanics, Institute of Mechanics, Chinese Academy of Sciences, Beijing, 100190, China
3.University of Nottingham, Gas and Transmissions Research Centre, Nottingham, NG7 2TU, United Kingdom
4.ETHZ, Labor für Kernenergiesysteme, Sonneggstrasse 3, Zürich, 8092, Switzerland
Recommended Citation
GB/T 7714
Niffenegger M,Garrido OC,Mora DF,et al. Uncertainties in pressurized thermal shock analyses[C]American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP,2019.
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