Computational fluid dynamics study of pressurized thermal shock phenomena in the reactor pressure vessel

Sharabi, Medhat; González-Albuixech, V.F.; Lafferty, Nathan; Ničeno, Bojan; Niffenegger, Markus

doi:10.1016/j.nucengdes.2015.10.014

Cited by 17 publications

(7 citation statements)

References 18 publications

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“…All the simulations in the current study were conducted making use of the finer mesh shown in Figure A,B. Further details about mesh strategy adopted in the present study can be found in Sharabi et al The shear stress transport k‐ω model is used to model the turbulence, and the y + for the first node beside the wall is around 100. Second‐order discretization schemes are adopted for the convection and transient terms in the governing equation.…”

Section: Pts Loading Transient Calculationsmentioning

confidence: 99%

Effect of non‐uniform reactor cooling on fracture and constraint of a reactor pressure vessel

Qian

Niffenegger

Sharabi

et al. 2018

Fatigue Fract Eng Mat Struct

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In the lifetime prediction and extension of a nuclear power plant, a reactor pressure vessel (RPV) has to demonstrate the exclusion of brittle fracture. This paper aims to apply fracture mechanics to analyse the non‐uniform cooling effect in case of a loss‐of‐coolant accident on the RPV integrity. A comprehensive framework coupling reactor system, fluid dynamics, fracture mechanics, and probabilistic analyses for the RPVs integrity analysis is proposed. The safety margin of the allowed RTNDT is increased by more than 16°C if a probabilistic method is applied. Considering the non‐uniform plume cooling effect increases KI more than 30%, increases the failure frequency by more than 1 order of magnitude, and increases the crack tip constraint due to the resulting higher stress. Thus, in order to be more realistic and not to be nonconservative, 3D computational fluid dynamics may be required to provide input for the fracture mechanics analysis of the RPV.

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Section: Pts Loading Transient Calculationsmentioning

confidence: 99%

Effect of non‐uniform reactor cooling on fracture and constraint of a reactor pressure vessel

Qian

Niffenegger

Sharabi

et al. 2018

Fatigue Fract Eng Mat Struct

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“…Thanks to two-phase computational fluid dynamics and 3D finite element analysis, validated by experimental programs (e.g., [4,5,6,7,8]), it is possible to precisely assess stresses and temperatures in the vessel wall during such events. Knowing the steel mechanical properties and the size of the defects it may contain, that assessment allows determining whether the vessel incurs any risk of brittle fracture.…”

Section: Rpv Safetymentioning

confidence: 99%

“…RT NDT is determined from Charpy and Pellini tests (nilductility temperature) as specified in codes. The Reference Curve -often named "the million dollar curve" (6) -was drawn on the lowest K IC values (7) available at that time for non-irradiated pressure vessel steels in the US (Fig. 6).…”

Section: A Reference Curve For Rpvsmentioning

confidence: 99%

60th Anniversary of electricity production from light water reactors: Historical review of the contribution of materials science to the safety of the pressure vessel

Duysen

Bellefon

2017

Journal of Nuclear Materials

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The first light water nuclear reactor dedicated to electricity production was commissioned in Shippingport, Pennsylvania in the United States in 1957. Sixty years after the event, it is clear that this type of reactor will be a major source of electricity and one of the key solutions to limit climate change in the 21 st century. This article pays homage to the teams that contributed to this achievement by their involvement in research and development and their determination to push back the frontiers of knowledge. Via a few examples of scientific or technological milestones, it describes the evolution of ideas, models, and techniques during the last 60 years, and gives the current state-of-the-art in areas related to the safety of the reactor pressure vessel. Among other topics, it focuses on vessel manufacturing, steel fracture mechanics analysis, and understanding of irradiation-induced damage.

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“…Unlike these codes, high fidelity methods allow the detailed geometry to be taken into account and to predict multidimensional features of PTS in the RPV. In particular, CFD is proven to be able to represent the PTS temperature evolution in detail in the coolant during the transient [10]. Thus, the application of CFD has the ability to represent three-dimensional features of the flow that directly affect the structural response.…”

Section: Introductionmentioning

confidence: 99%

Demonstration of CFD to support the coupled analysis of a reactor pressure vessel subjected to pressurized thermal shock

Shaver

Merzari

2021

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Computational fluid dynamics study of pressurized thermal shock phenomena in the reactor pressure vessel

Cited by 17 publications

References 18 publications

Effect of non‐uniform reactor cooling on fracture and constraint of a reactor pressure vessel

Effect of non‐uniform reactor cooling on fracture and constraint of a reactor pressure vessel

60th Anniversary of electricity production from light water reactors: Historical review of the contribution of materials science to the safety of the pressure vessel

Demonstration of CFD to support the coupled analysis of a reactor pressure vessel subjected to pressurized thermal shock

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