Uncertainties in pressurized thermal shock analyses
文献类型：会议论文
| 作者 | Niffenegger M; Garrido OC; Mora DF; Qian GA(钱桂安) ; Mukin R; Sharabi M; Lafferty N; Niceno B; Qian GA(钱桂安)
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| 出版日期 | 2019 |
| 会议日期 | July 14, 2019 - July 19, 2019 |
| 会议地点 | San Antonio, TX, United states |
| 关键词 | Computational fluid dynamics Finite element method Pressurized thermal shock Probabilistic fracture mechanics Warm pre-stressing |
| 英文摘要 | Integrity 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. |
| 会议录 | American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP
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| 语种 | 英语 |
| URL标识 | 查看原文 |
| ISBN号 | 9780791858943 |
| 源URL | [http://dspace.imech.ac.cn/handle/311007/85117]  |
| 专题 | 力学研究所_非线性力学国家重点实验室 |
| 作者单位 | 1.ETHZ, Labor für Kernenergiesysteme, Sonneggstrasse 3, Zürich, 8092, Switzerland 2.University of Nottingham, Gas and Transmissions Research Centre, Nottingham, NG7 2TU, United Kingdom 3.State Key Laboratory of Nonlinear Mechanics, Institute of Mechanics, Chinese Academy of Sciences, Beijing, 100190, China 4.Paul Scherrer Institut, Nuclear Energy and Safety Department, Villigen PSI, CH-5232, Switzerland |
| 推荐引用方式 GB/T 7714 | Niffenegger M,Garrido OC,Mora DF,et al. Uncertainties in pressurized thermal shock analyses[C]. 见:. San Antonio, TX, United states. July 14, 2019 - July 19, 2019. |
入库方式： OAI收割
来源：力学研究所
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