Fracture Mechanics Analysis of a Pressure Vessel with a Semi-Elliptical Surface Crack Using Elastic-Plastic Finite Element Calculations

2008 ◽  
pp. 617-617-15 ◽  
Author(s):  
D Aurich ◽  
W Brocks ◽  
H-D Noack ◽  
H Veith
Keyword(s):  
Finite Element ◽  
Fracture Mechanics ◽  
Surface Crack ◽  
Pressure Vessel ◽  
Elastic Plastic ◽  
Finite Element Calculations ◽  
Mechanics Analysis

scholarly journals Elastic-plastic fracture mechanics analysis by combination of boundary element and finite element methods.

1984 ◽  
Vol 50 (460) ◽  
pp. 1963-1971 ◽  
Author(s):  
Kikuo KISHIMOTO ◽  
Ishou YAMAGUCHI ◽  
Masayoshi TACHIHARA ◽  
Shigeru AOKI ◽  
Masaru SAKATA
Keyword(s):  
Finite Element ◽  
Fracture Mechanics ◽  
Boundary Element ◽  
Finite Element Methods ◽  
Elastic Plastic ◽  
Mechanics Analysis

Approximate J Estimates for Circumferential Cracks in between Elbows and Attached Pipes

2007 ◽  
Vol 345-346 ◽  
pp. 521-524
Author(s):  
Tae Kwang Song ◽  
Chang Kyun Oh ◽  
Yun Jae Kim ◽  
Jong Sung Kim ◽  
Tae Eun Jin
Keyword(s):  
Finite Element ◽  
Fracture Mechanics ◽  
Closed Form ◽  
Limit Load ◽  
Small Strain ◽  
Straight Pipe ◽  
Popular Approach ◽  
Elastic Plastic ◽  
Reference Stress ◽  
Mechanics Analysis

The present work proposes a method for elastic-plastic fracture mechanics analysis of the circumferential through-wall crack in between elbows and attached straight pipes, subject to in-plane bending. Based on small strain finite element limit analyses, closed-form limit load solutions are given first. Then applicability of the reference stress based method to approximately estimate J is proposed. One interesting finding is that a popular approach to assume that the crack locates in the straight pipe could lead to significantly different assessment results.

A Fracture Mechanics Evaluation of BWR Vessel Water Level Instrumentation Nozzle P-T Curve Assessment Including Impact of Irradiation Effects

2012 ◽  
Author(s):  
Hardayal S. Mehta ◽  
Lori J. Tilly ◽  
Donald A. Sampson
Keyword(s):  
Finite Element ◽  
Fracture Mechanics ◽  
Water Level ◽  
Pressure Vessel ◽  
Irradiation Effects ◽  
Linear Elastic ◽  
Mechanics Analysis ◽  
Elastic Fracture ◽  
The Impact ◽  
Reactor Pressure

This paper describes the evaluation performed to determine the bounding T-RTNDT for the Boiling Water Reactor (BWR) Water Level Instrumentation (WLI) nozzle for use in establishing reactor pressure vessel Pressure-Temperature (P-T) curves. The evaluation used finite element based fracture mechanics to augment the methods described in the ASME Boiler & Pressure Vessel Code, Section XI, Appendix G. A 3-D finite element linear elastic fracture mechanics analysis was conducted to determine the mode I stress intensity factor at the tip of a 1/4 thickness postulated flaw in the nozzle blend radius. Also included is a general discussion on the impact on the P-T curves of the postulated irradiation shift in RTNDT at the WLI nozzle.

Reactor Pressure Vessel Integrity Assessment: French Simplified Analysis Method Applied to Underclad Postulated Defect in Nozzle

2016 ◽  
Author(s):  
Adolfo Arrieta-Ruiz ◽  
Eric Meister ◽  
Stéphane Vidard
Keyword(s):  
Fracture Mechanics ◽  
Fracture Risk ◽  
Pressure Vessel ◽  
Reactor Pressure Vessel ◽  
Core Area ◽  
Integrity Assessment ◽  
Elastic Plastic ◽  
The Core ◽  
Simplified Method ◽  
Reactor Pressure

Structural integrity of the Reactor Pressure Vessel (RPV) is one of the main concerns regarding safety and lifetime of Nuclear Power Plants (NPP) since this component is considered as not reasonably replaceable. Fast fracture risk is the main potential damage considered in the integrity assessment of RPV. In France, deterministic integrity assessment for RPV vis-à-vis the brittle fracture risk is based on the crack initiation stage. As regards the core area in particular, the stability of an under-clad postulated flaw is currently evaluated under a Pressurized Thermal Shock (PTS) through a dedicated fracture mechanics simplified method called “beta method”. However, flaw stability analyses are also carried-out in several other areas of the RPV. Thence-forward performing uniform simplified inservice analyses of flaw stability is a major concern for EDF. In this context, 3D finite element elastic-plastic calculations with flaw modelling in the nozzle have been carried out recently and the corresponding results have been compared to those provided by the beta method, codified in the French RSE-M code for under-clad defects in the core area, in the most severe events. The purpose of this work is to validate the employment of the core area fracture mechanics simplified method as a conservative approach for the under-clad postulated flaw stability assessment in the complex geometry of the nozzle. This paper presents both simplified and 3D modelling flaw stability evaluation methods and the corresponding results obtained by running a PTS event. It shows that the employment of the “beta method” provides conservative results in comparison to those produced by elastic-plastic calculations for the cases here studied.

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
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