The Effect of Postulated Flaws on the Structural Integrity of RPV During PTS

Jhung, Myung Jo; Choi, Young Hwan; Chang, Yoon‐Suk; Kim, Jong Wook

doi:10.5516/net.2007.39.5.647

Cited by 7 publications

(7 citation statements)

References 4 publications

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“…During transient loading, the existence of cracks threatens the structural integrity of the RPV. The critical crack size has been analysed through fracture mechanics calculations for some well-known types of cracks such as through-clad cracks, semielliptical underclad cracks, and fully elliptical underclad cracks (Jhung et al, 2007). Through-clad cracking has been widely considered in many studies, including round robin studies, on the structural integrity of RPVs through both deterministic (Jhung et al, 2009) and probabilistic fracture mechanics analysis (Chen et al, 2015).…”

Section: Introductionmentioning

confidence: 99%

“…Through-clad cracking has been widely considered in many studies, including round robin studies, on the structural integrity of RPVs through both deterministic (Jhung et al, 2009) and probabilistic fracture mechanics analysis (Chen et al, 2015). The effect of postulated cracks on the structural integrity of a PWR RPV was analysed by a deterministic method (Jhung et al, 2007) and fracture mechanical analysis for a Water Water Energetic Reactor (WWER) RPV under a thermal shock transient (Abendroth and Altstadt, 2007). In addition, probabilistic fracture mechanics analysis of VVER was performed for several PTS loading transients with the appearance of through-clad cracking (Pistora et al, 2014).…”

Section: Introductionmentioning

confidence: 99%

“…However, in practice, this crack has been the consequence of the welding process (USNRC, 2011) and was able to be detected inside the wall thickness of a real cladded RPV in 1986 (Gruber et al, 1986). From deterministic analysis results, the stress intensity factors in underclad cracking are two-times smaller than those of through-clad cracking and are almost negligible at the deepest point (Jhung et al, 2007). However, after long-time operation of an RPV under severe conditions, there is nothing to ensure that cracking does not threaten the structural integrity of an RPV.…”

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Probabilistic fracture mechanics analysis of reactor pressure vessel with underclad and through-clad cracks under pressurised thermal shock transient

Chen

Ting

Nguyễn

et al. 2018

IJNEST

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Semi-elliptical underclad cracks resulting from the fabrication process of a reactor pressure vessel (RPV) were able to be detected by nondestructive testing method. Meanwhile, after long-term operation under severe conditions, such as high temperature, high pressure, and irradiation, the RPV becomes brittle and susceptible to damage, especially when subjected to pressurised thermal shocks (PTS). Therefore, the probabilistic fracture mechanics (PFM) analysis of RPV with the crack should be applied to evaluate the operation safety. To the best of the authors' knowledge, few studies or computer codes have applied PFM analysis for such cracks. Therefore, this study conducts PFM analysis for cracks by modifying the calculation procedure of FAVOR 12.1 computer code. The results show that during the K.T. Chen et al.lifetime of a nuclear power plant, such cracks will not threaten the RPV's safety. Additionally, three methods were proposed to improve FAVOR 12.1's ability to perform PFM analysis for axial through-clad cracking. , T.L. (2018) 'Probabilistic fracture mechanics analysis of reactor pressure vessel with underclad and through-clad cracks under pressurised thermal shock transient', Int.

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Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Probabilistic fracture mechanics analysis of reactor pressure vessel with underclad and through-clad cracks under pressurised thermal shock transient

Chen

Ting

Nguyễn

et al. 2018

IJNEST

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“…Therefore, it is necessary to evaluate the structural integrity of a reactor pressure vessel under a PTS event. 1,2) According to Regulatory Guide 1.154, 3) the plant-specific analysis should include both probabilistic and deterministic fracture mechanics analyses. The probabilistic analyses should be used to determine the statistical likelihood of vessel through-wall crack penetration assuming a crack size distribution appropriately justified for the vessel being analyzed and appropriate standard deviations and distribution of the significant input parameter such as material properties.…”

Section: Introductionmentioning

confidence: 99%

Structural Integrity of Reactor Pressure Vessel for Small Break Loss of Coolant Accident

Jhung

Choi

JANG

2009

Journal of Nuclear Science and Technology

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Plant-specific analyses of the typical pressurized water reactor in Korea are performed to assure the structural integrity of the reactor pressure vessel during transient, which is expected to initiate pressurized thermal shock event. The deterministic analysis is performed to determine the critical time interval in the transient during which mitigating action can be effective. Also, the failure probability is obtained by performing probabilistic fracture mechanics analysis. In addition, several sensitivity analyses are performed for warm prestressing, plastic zone correction, and simulation option to calculate fracture toughness etc. to assess its effect on the failure probability.

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“…This approach in followed basically for saving computational resources, an example of this approach can be found in the ref. [19].…”

Section: Structural Mechanics Analysismentioning

confidence: 99%

Methodology for Pressurized Thermal Shock Analysis in Nuclear Power Plant

Araneo¹,

D'Auria²

2012

Applied Fracture Mechanics

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The Effect of Postulated Flaws on the Structural Integrity of RPV During PTS

Cited by 7 publications

References 4 publications

Probabilistic fracture mechanics analysis of reactor pressure vessel with underclad and through-clad cracks under pressurised thermal shock transient

Probabilistic fracture mechanics analysis of reactor pressure vessel with underclad and through-clad cracks under pressurised thermal shock transient

Structural Integrity of Reactor Pressure Vessel for Small Break Loss of Coolant Accident

Methodology for Pressurized Thermal Shock Analysis in Nuclear Power Plant

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