Abstract
In this paper, the stress analysis of the support structure (skirt) of a Boiling Water Reactor (BWR-5) vessel is presented. Three transient loading conditions, which take place during the life of the plant, were evaluated, in order to determine the structural integrity under fatigue loading. The concept of Cumulative Usage Fatigue (CUF) was used. The guidelines of the subsection NB and subsection NF of Section III of the ASME Code were taken into account in the evaluation in conjunction with the Finite Element Analyses (FEA). In addition, the environmental fatigue penalty factors (Fen) were also considered during the evaluation. The environmental conditions affected the integrity of the skirt. Besides, a perturbation in the stresses was observed due to the dynamic forces generated by the jet pumps, which increased the CUF in the skirt.
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Abbreviations
- BWR:
-
Boiling Water Reactor
- CUF:
-
Cumulative Usage Factor
- FEA:
-
Finite Element Analysis
- NPP:
-
Nuclear Power Plant
- FEM:
-
Finite Element Method
- PWR:
-
Pressure Water Reactor
- PVR:
-
Pressure Vessel Reactor
- AEF:
-
Assisted Environmental Fatigue
- ppm:
-
Parts per million
- DO:
-
Dissolved Oxygen
- CS:
-
Carbon Steel
- LAS:
-
Low Alloy Steel
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Acknowledgements
The grant for the development of the project 211704 awarded by the National Council of Science and Technology (CONACYT) is kindly acknowledged.
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Grijalba, Y.L. et al. (2019). Evaluation of the Structural Integrity of a Boiling Water Reactor Skirt Under Stationary and Transient Loading Conditions. In: Öchsner, A., Altenbach, H. (eds) Engineering Design Applications. Advanced Structured Materials, vol 92. Springer, Cham. https://doi.org/10.1007/978-3-319-79005-3_31
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DOI: https://doi.org/10.1007/978-3-319-79005-3_31
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