Residual life assessment of major light water reactor components: Overview

Shah, V.N.; MacDonald, P.E.; Amar, Abdelouahed; Bakr, Marwa H.; Beaudoin, B.F.; Buescher, B.J.; Conley, D.A.; Drahos, F.R.; Gardner, Julie; Garner, R.W.; Kirkwood, B.J.; Meyer, Lucas; Server, W.L.; Siegel, E.A.; Sinha, Upasana; Ware, A.G.

doi:10.2172/5067353

Cited by 15 publications

(10 citation statements)

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“…The Average Strain Energy Density (ASED) criterion has been widely used to predict fracture in various materials since its introduction in the 1970s by Sih [21] and its further development carried out by Lazzarin and Zambardi [6,[22][23][24]. The criterion states that the fracture occurs when the mean value of strain energy density (W) within a control volume equals the critical ASED value (W c ), as expressed in Equation (1).…”

Section: The Average Strain Energy Density Criterionmentioning

confidence: 99%

“…Structural steels are widely used in engineering structures, particularly in the construction industry. Brittle fracture is a major concern in practical situations, such as the cleavage fracture of reactor pressure vessels in nuclear power plants [1]. Structural steels can experience cleavage fracture at low temperatures, either in the brittle regime (lower shelf, LS) or in the Ductile-to-Brittle Transition Range (DBTR).…”

Section: Introductionmentioning

confidence: 99%

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Fracture Load Prediction of Non-Linear Structural Steels through Calibration of the ASED Criterion

Sánchez

Cicero

Arrieta

et al. 2023

Metals

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In this work, the application of the Average Strain Energy Density (ASED) criterion for the estimation of failure loads in materials with nonlinear behavior containing U-shaped notches is presented. The ASED criterion was originally defined to predict failure in the presence of notches in materials with linear-elastic behavior. However, most structural materials (e.g., ferritic-pearlitic steels) can develop non-linear behavior (e.g., elastoplastic). In this sense, this work proposes to extend the use of the ASED criterion to materials that exhibit plasticity by a thorough calibration of their characteristic parameters, and the subsequent extrapolation of the liner-elastic formulation of the ASED criterion to non-linear situations. To validate this methodology, a wide range of structural steels (S275JR, S355J2, S460M, and S690Q) were used operating in the ductile-to-brittle transition range, with six different notch radii (0 mm, 0.15 mm, 0.25 mm, 0.50 mm, 1.0 mm, and 2.0 mm). The results obtained demonstrate that the proposed calibration of the ASED criterion allows for accurate predictions of failure loads. Therefore, it is shown that, for the notch radii analyzed in this work and for testing temperatures within the material ductile-to-brittle transition range, it is possible to extrapolate the ASED criterion to obtain estimates of failure loads in materials with U-shaped notches that exhibit ductile behavior.

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Section: The Average Strain Energy Density Criterionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Fracture Load Prediction of Non-Linear Structural Steels through Calibration of the ASED Criterion

Sánchez

Cicero

Arrieta

et al. 2023

Metals

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“…Materials used in shields are SA302B, SA302B modified, Sa533B-1, SA533B-1 low cu/p, SA508-2 and SA508-3 in RPV, the Earliest RPVs used SA302B steel. Most vessels are made from SA533B Latest RPV's used low Cu/P contents inside RPV is lined with stainless steel (types 304(early), 308 & 309) to reduce corrosion [11]. Table 1 shows PWR vessel materials [12].…”

Section: Introductionmentioning

confidence: 99%

The Use of the Stopping and Range of Ions in Matter Code for Calculation of Damage in Three Different Types of Steel

Qadr

2024

Journal of Physical Chemistry and Functional Materials

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In recent years, nuclear power plants have been built worldwide. This amount large of power is better than other energy sources for the environment, it does not have a greenhouse gas. A pressurized water reactor (PWR) is a type of light water reactor to generate electricity and it needed enriched Uranium and large cost. The purpose of this work was to investigate three different types of steel for PWR reactor vessels such as SA30400, SA302B and SA355B-1 steel. The result shows that SA355B-1 performs better than the other. On the other hand, phonons, ionization and collision events show very little damage to all materials.

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“…The key factors that can cause thermal fatigue near the T-junction are (1) thermal cycling, which is the process of cycling of the interface of thermally stratified fluids [5], and (2) thermal striping, which is defined as a quasirandom temperature fluctuation produced by the incomplete mixing of fluids [6,7]. Several pipe failures and leakage incidents in NPPs have been attributed to thermal striping and fatigue [8][9][10], which highlights the need to better understand the flow physics underlying thermal fatigue for plant safety and long-term component reliability, as well as plant aging assessment and life extension (PLEX) [11,12].…”

Section: Introductionmentioning

confidence: 99%

Mean Flow, Turbulent Structures, and SPOD Analysis of Thermal Mixing in a T-Junction with Variation of the Inlet Flow Profile

et al. 2022

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This paper investigates the effects of different inlet flow profiles on thermal mixing within a T-junction using CFD simulations with the IDDES-SST turbulence model. The different combinations of inlet flow profiles are related to different stage in the flow entry region. The effects of the inlet flow profile on the mean and transient flow behaviour are assessed, while a spectral proper orthogonal decomposition and power spectral density analysis are performed to assess the underlying flow structures and the predominant frequency modes. It is found that the vortical structures associated with the horseshoe and hovering vortex systems consist of a single roll-up vortex for cases with uniformly distributed boundary conditions (BCs) at the branch inlet whereas a double roll-up vortex is observed for the other cases. The double roll-up vortex enhances the mixing locally due to the entrainment of fluid from the branch pipe in these vortical structures, which then results in a lower mean temperature distribution. The appearance of the secondary vortex pair and the nested vortices is delayed for cases with uniformly distributed BCs at the branch inlet, which again results in lower thermal mixing and consequently higher values of mean temperature when compared with the other cases. It is also found that the vorticity related to the counter-rotating vortex pair as well as to the second pair of vortices rotating in the opposite direction is higher for cases with uniformly distributed BCs at the branch inlet. Lastly, the combinations of inlet flow profiles lead to different coherent structures, and the dominant frequencies are of a Strouhal number of around 0.7 for uniformly distributed profiles at the branch inlet and in the range 0.4–0.5 for the other cases.

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Residual life assessment of major light water reactor components: Overview

Cited by 15 publications

References 0 publications

Fracture Load Prediction of Non-Linear Structural Steels through Calibration of the ASED Criterion

Fracture Load Prediction of Non-Linear Structural Steels through Calibration of the ASED Criterion

The Use of the Stopping and Range of Ions in Matter Code for Calculation of Damage in Three Different Types of Steel

Mean Flow, Turbulent Structures, and SPOD Analysis of Thermal Mixing in a T-Junction with Variation of the Inlet Flow Profile

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