scholarly journals Sensitivity Analysis of Failure Probability on PTS Benchmark Problems of Pressure Vessel Using a Probabilistic Fracture Mechanics Analysis Code.

2001 ◽  
Vol 44 (1) ◽  
pp. 130-137 ◽  
Author(s):  
Yinsheng LI ◽  
Daisuke KATO ◽  
Katsuyuki SHIBATA
Keyword(s):  
Sensitivity Analysis ◽  
Fracture Mechanics ◽  
Failure Probability ◽  
Pressure Vessel ◽  
Benchmark Problems ◽  
Probabilistic Fracture Mechanics ◽  
Mechanics Analysis

scholarly journals Recent verification activities on probabilistic fracture mechanics analysis code PASCAL4 for reactor pressure vessel

2020 ◽  
Vol 7 (3) ◽  
pp. 19-00573-19-00573
Author(s):  
Kai LU ◽  
Jinya KATSUYAMA ◽  
Yinsheng LI ◽  
Yuhei MIYAMOTO ◽  
Takatoshi HIROTA ◽  
...  
Keyword(s):  
Fracture Mechanics ◽  
Pressure Vessel ◽  
Reactor Pressure Vessel ◽  
Probabilistic Fracture Mechanics ◽  
Mechanics Analysis ◽  
Reactor Pressure

Development of Probabilistic Fracture Mechanics Analysis Codes for Reactor Pressure Vessels Considering Recent Embrittlement Model and Calculation Method of SIF: Progress of the Work

2016 ◽  
Author(s):  
Jongmin Kim ◽  
Bongsang Lee ◽  
Taehyun Kim ◽  
Yoonsuk Chang
Keyword(s):  
Stress Intensity ◽  
Fracture Mechanics ◽  
Pressure Vessel ◽  
Calculation Method ◽  
Reactor Pressure Vessel ◽  
Radiation Embrittlement ◽  
Calculation Methods ◽  
Probabilistic Fracture Mechanics ◽  
Mechanics Analysis ◽  
Reactor Pressure

It is widely recognized that the state of knowledge and data for the probabilistic calculations which had been proposed in the early 1980s made a conservative treatment of several key factors and models. Recently, applications of some new radiation embrittlement model, material database, calculation method of stress intensity factors and others which can improve fracture mechanics assessment of reactor pressure vessel (RPV) are introduced. This improvement on the accuracy and reliability of the probabilistic fracture mechanics (PFM) analysis necessitated changes in PFM analysis procedures and calculations. Modification and application of newly developed models and calculation methods are the main target of developing a probabilistic fracture mechanics analysis code based on the structure of existing R-PIE and VISA computer code to reflect the latest technical basis. Failure probabilities of reactor pressure vessel under pressurized thermal shock (PTS) conditions were calculated through finite difference method (FDM) and Monte Carlo simulation techniques with user friendly graphic interface. Moreover, various radiation embrittlement models and calculation methods of stress intensity factor at crack tip based on AFCEN code are applied and verified in the present work.

Improvement of Probabilistic Fracture Mechanics Analysis Code for Reactor Piping Considering Large Earthquakes

2014 ◽  
Author(s):  
Yoshihito Yamaguchi ◽  
Jinya Katsuyama ◽  
Makoto Udagawa ◽  
Kunio Onizawa ◽  
Yutaka Nishiyama ◽  
...  
Keyword(s):  
Fracture Mechanics ◽  
Failure Probability ◽  
Seismic Loading ◽  
Earthquake Magnitude ◽  
Sensitivity Analyses ◽  
Probabilistic Fracture Mechanics ◽  
Probabilistic Evaluation ◽  
Mechanics Analysis ◽  
Growth Evaluation ◽  
Large Earthquakes

The probabilistic fracture mechanics analysis code PASCAL-SP is improved by introducing crack-growth evaluation methods based on J-integrals, including calculation functions of J-integral values for semi-elliptical surfaces and through-wall cracks in pipes. Using the improved PASCAL-SP, sensitivity analyses that varied parameters such as earthquake magnitude were carried out on the basis of probabilistic evaluation. Results obtained from sensitivity analyses are also presented, e.g., the effect of earthquake magnitude on failure probability. The improved PASCAL-SP makes evaluation of the failure probability of piping under large seismic loading possible.

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