Please use this identifier to cite or link to this item: http://hdl.handle.net/11455/97292
標題: PWR 與 VVER 反應爐壁在暫態高溫高壓負載下之機率破裂力學分析
Probabilistic Fracture Mechanics Analysis of PWR and VVER Reactor Pressure Vessel under Pressurized Thermal Shock Transients
作者: 阮英俊
Anh Tuan Nguyen
關鍵字: 波懷裡學
反應爐
應力分析
PWR
VVER
PFM
PTS
Reactor Pressure Vessel
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摘要: The reactor pressure vessel (RPV), the most important component of both pressurized water reactor (PWR) and water water energetic reactor (VVER), becomes brittle after long-term operation in severe conditions (e.g., neutron radiation, high pressure, and high temperature). As such, in this study the structural integrity of the PWR and VVER RPV are considered under PTS transients with different conditions. For the PWP RPV, the effects of a semi-elliptical underclad crack on RPV integrity is investigated by proposed methods. Those cracks resulting from the fabrication process of a reactor pressure vessel (RPV) were able to be detected by non-destructive testing method. The probabilistic fracture mechanics (PFM) analysis of RPVs with the cracks should be applied to evaluate the safety of operation. To the best of the authors’ knowledge, few studies or computer codes have applied probabilistic assessment for such cracks. Therefore, this study conducts PFM analysis for the cracks by modifying the calculation procedure of FAVOR 12.1. The results show that in the conditions of this study such cracks do not threaten the safety of the RPV. Additionally, three methods were proposed to improve FAVOR 12.1’s ability to perform PFM analysis for axial through clad cracking. This study improves FAVOR 12.1 to allow it to perform PFM analysis for semi-elliptical underclad crack and for wider range of through clad crack. For VVER RPV, the cladding consists of austenitic stainless steel to protect the RPV wall against corrosion. Otherwise, the stainless-steel cladding affects the fracture mechanics of the RPV under some transient conditions such as pressurized thermal shock (PTS). In this study, the computer code FAVOR 12.1 is used to estimate the effect of the cladding thickness on the structural integrity of VVER RPV by performing DFM and PFM analyses for RPV under transient pressurized thermal shock. A thoroughly clad, semi-elliptical geometry is assumed in the analysis.
URI: http://hdl.handle.net/11455/97292
文章公開時間: 10000-01-01
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