Failure probability study of HTR graphite component using microstructure-based model

Yu, Suyuan; Fang, Xiang; Wang, Haitao; Li, Chenfeng

doi:10.1016/j.nucengdes.2012.08.019

Cited by 11 publications

(4 citation statements)

References 19 publications

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“…The Burchell model, which is founded from the microfracture mechanism of graphite, is an evolution of the Rose and Tucker fracture model which was developed in the 1970s [5]. It has been verified that the Burchell model is able to simulate the tensile test results in Figure 2 very well [13].…”

Section: Burchellmentioning

confidence: 90%

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The Stress and Reliability Analysis of HTR’s Graphite Component

Fang

Wang²,

Yu³

2014

Science and Technology of Nuclear Installations

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The high temperature gas cooled reactor (HTR) is developing rapidly toward a modular, compact, and integral direction. As the main structure material, graphite plays a very important role in HTR engineering, and the reliability of graphite component has a close relationship with the integrity of reactor core. The graphite components are subjected to high temperature and fast neutron irradiation simultaneously during normal operation of the reactor. With the stress accumulation induced by high temperature and irradiation, the failure risk of graphite components increases constantly. Therefore it is necessary to study and simulate the mechanical behavior of graphite component under in-core working conditions and forecast the internal stress accumulation history and the variation of reliability. The work of this paper focuses on the mechanical analysis of pebble-bed type HTR's graphite brick. The analysis process is comprised of two procedures, stress analysis and reliability analysis. Three different creep models and two different reliability models are reviewed and taken into account in simulation. The stress and failure probability calculation results are obtained and discussed. The results gained with various models are highly consistent, and the discrepancies are acceptable.

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Section: Burchellmentioning

confidence: 90%

“…where is the representative volume of integration point and is the volume of graphite component; = ∑ . The failure probability of the graphite component is then expressed as [13]…”

Section: Weibull Model the Fitting Curve Methods Is Used Inmentioning

confidence: 99%

The Stress and Reliability Analysis of HTR’s Graphite Component

Fang

Wang²,

Yu³

2014

Science and Technology of Nuclear Installations

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“…This technique for the filler particle segmentation in Gilsocarbon graphite has potential application in the quantitative 3D characterisation of microstructures, for instance to support investigations of the effects of microstructure variations on mechanical properties [37][38][39] of the small specimens, which may control data scatter. Data on microstructure variations within manufactured components, which could be measured in quite large datasets using this method, could also provide insights into the variability of their performance [40][41][42]. The technique may be transferred to other materials, such as ceramic composites [43][44][45][46], that contain different pore structures in order to perform a segmentation of their individual components for modelling.…”

Section: Multifractal-based Algorithm For Filler Particle Segmentationmentioning

confidence: 99%

Multifractal-based assessment of Gilsocarbon graphite microstructures

Vertyagina

Marrow

2016

Carbon

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“…It is important to be able to forecast the risk of fracture in the design process and for management of the reactor lifetime [14,15], and this requires knowledge of the fracture resistance of irradiated graphite.…”

Section: Introductionmentioning

confidence: 99%

Assessment of the fracture toughness of neutron-irradiated nuclear graphite by 3D analysis of the crack displacement field

Jin

Wade-Zhu

Chen

et al. 2021

Carbon

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Digital volume correlation of in situ synchrotron X-ray computed tomographs has been used to measure the three-dimensional displacement fields around quasi-static propagating cracks in neutron irradiated and unirradiated graphite in small test specimens of the double cleavage drilled compression geometry. The crack tip location and crack opening were extracted from the displacement fields using a phase congruency edge detection method as cracks were propagated over ~5 mm. The cracks propagated in mode I, maintaining a constant crack opening angle that was ~50% smaller for the irradiated graphite. 3D finite element simulations, using the measured full field displacements as boundary conditions, obtained the critical elastic strain energy release rate for crack propagation by calculation of the domain * Author's copy of paper accepted for publication in Carbon,

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Failure probability study of HTR graphite component using microstructure-based model

Cited by 11 publications

References 19 publications

The Stress and Reliability Analysis of HTR’s Graphite Component

The Stress and Reliability Analysis of HTR’s Graphite Component

Multifractal-based assessment of Gilsocarbon graphite microstructures

Assessment of the fracture toughness of neutron-irradiated nuclear graphite by 3D analysis of the crack displacement field

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