NDLI: Elastoplastic Fracture Resistance Analysis of NPP Primary Circuit Equipment Elements

Content Provider	Springer Nature Link
Author	Kharchenko, V. V. Pimiv, V. A. Chirkov, À. Yu. Kîbel’skii, S. V. Kravchenkî, V. I.
Copyright Year	2013
Abstract	Ñurrent calculation analysis approaches to the fracture resistance assessment for main equipment elements of the WWER NPP primary circuit are considered. It is noted that the solution of the problems of justifying safe operation, assessment of the integrity and extension of the lifetime of the reactor pressure vessel is essentially dependent on the results of calculations of the kinetics of the stress strain state, a proper consideration of the residual welding stress and strain fields, reliable evaluation of non-linear fracture mechanics parameters. A general methodology is developed for a calculated analysis of the fracture resistance of WWER reactor pressure vessels in the simulation of emergency cooling conditions. The main statements in the elastoplastic calculation of the kinetics of the stress strain state for reactor pressure vessels are formulated with consideration of the residual welding stress and strain fields, and the calculation procedure for determining the fracture parameters of the postulated crack is presented. Using the calculation methods and software product developed, a significant influence of such factors as consideration of the thermomechanical loading history and elastoplastic deformation of the metal in the vicinity of the postulated crack front, different ways of taking into consideration the residual welding stress level, the regularity and density of the finite element mesh in the vicinity of the calculated crack front, the procedure for calculating the elastoplastic fracture parameters in discrete finite element method models on the calculated fracture resistance assessment of WWER-1000 reactor pressure vessels is shown. It is found that the neglect of the loading history and residual stress level after heat treatment results in a non-conservative assessment of the fracture resistance for the collector-to-nozzle welded joint in the PGV-1000 steam generator in the simulation of the operating cycle of loading.
Starting Page	397
Ending Page	405
Page Count	9
File Format	PDF
ISSN	00392316
Journal	Strength of Materials
Volume Number	45
Issue Number	4
e-ISSN	15739325
Language	English
Publisher	Springer US
Publisher Date	2013-10-15
Publisher Place	Boston
Access Restriction	One Nation One Subscription (ONOS)
Subject Keyword	stress–strain state residual stresses stress intensity factor postulated crack reactor pressure vessel steam generator pressurized thermal shock mixed finite element scheme Characterization and Evaluation of Materials Structural Mechanics Mechanics
Content Type	Text
Resource Type	Article
Subject	Mechanics of Materials

Sl.	Authority	Responsibilities	Communication Details
1	Ministry of Education (GoI), Department of Higher Education	Sanctioning Authority	https://www.education.gov.in/ict-initiatives
2	Indian Institute of Technology Kharagpur	Host Institute of the Project: The host institute of the project is responsible for providing infrastructure support and hosting the project	https://www.iitkgp.ac.in
3	National Digital Library of India Office, Indian Institute of Technology Kharagpur	The administrative and infrastructural headquarters of the project	Dr. B. Sutradhar bsutra@ndl.gov.in
4	Project PI / Joint PI	Principal Investigator and Joint Principal Investigators of the project	Dr. B. Sutradhar bsutra@ndl.gov.in Prof. Saswat Chakrabarti will be added soon
5	Website/Portal (Helpdesk)	Queries regarding NDLI and its services	support@ndl.gov.in
6	Contents and Copyright Issues	Queries related to content curation and copyright issues	content@ndl.gov.in
7	National Digital Library of India Club (NDLI Club)	Queries related to NDLI Club formation, support, user awareness program, seminar/symposium, collaboration, social media, promotion, and outreach	clubsupport@ndl.gov.in
8	Digital Preservation Centre (DPC)	Assistance with digitizing and archiving copyright-free printed books	dpc@ndl.gov.in
9	IDR Setup or Support	Queries related to establishment and support of Institutional Digital Repository (IDR) and IDR workshops	idr@ndl.gov.in

The influence of thermomechanical loading history on the stress level in WWER NPP reactor pressure vessels under thermal shock

Effect of Stress Intensity Factor Estimation Scheme on the Failure Probability of RPV During Pressurized Thermal Shock

Stress-Strain State of the Coolant Collector-to-Nozzle Welded Joint in the PGV-1000M Steam Generator Under the Operating Loads with Consideration of Residual Manufacturing Stresses

Some Aspects of Inclusion of Loading History in the Fracture Strength Analysis of Reactor Pressure Vessels Under Thermal Shock Conditions

Fracture Mechanics Analyses of Embedded Cracks Under PTS and Effects of Residual Stresses

Stress and Fracture Mechanics Analyses of Boiling Water Reactor and Pressurized Water Reactor Pressure Vessel Nozzles

Measurement of residual stresses using fracture mechanics weight functions

Round robin analysis for probabilistic structural integrity of reactor pressure vessel under pressurized thermal shock

Development of Stress Intensity Factor Coefficients Database for a Surface Crack of an RPV Considering the Stress Discontinuity Between Cladding and Base Metal

Elastoplastic Fracture Resistance Analysis of NPP Primary Circuit Equipment Elements

Similar Documents

The influence of thermomechanical loading history on the stress level in WWER NPP reactor pressure vessels under thermal shock

Effect of Stress Intensity Factor Estimation Scheme on the Failure Probability of RPV During Pressurized Thermal Shock

Stress-Strain State of the Coolant Collector-to-Nozzle Welded Joint in the PGV-1000M Steam Generator Under the Operating Loads with Consideration of Residual Manufacturing Stresses

Some Aspects of Inclusion of Loading History in the Fracture Strength Analysis of Reactor Pressure Vessels Under Thermal Shock Conditions

Fracture Mechanics Analyses of Embedded Cracks Under PTS and Effects of Residual Stresses

Stress and Fracture Mechanics Analyses of Boiling Water Reactor and Pressurized Water Reactor Pressure Vessel Nozzles

Measurement of residual stresses using fracture mechanics weight functions

Round robin analysis for probabilistic structural integrity of reactor pressure vessel under pressurized thermal shock

Development of Stress Intensity Factor Coefficients Database for a Surface Crack of an RPV Considering the Stress Discontinuity Between Cladding and Base Metal

Elastoplastic Fracture Resistance Analysis of NPP Primary Circuit Equipment Elements