15th International Conference on 
Structural Mechanics in Reactor Technology


 

DIVISION G: FRACTURE MECHANICS

 

G01/1

Assessment of Cracked Components Subjected to High Thermal Stress
Weilin Zang

G01/2

Probabilistic Fracture Mechanics Analysis for Pipe Considering Dispersion of Seismic Loading
Hideo Machida

G01/3

Stress Analysis of a Nuclear Power Plant LP Turbine Rotor Disc Using Finite Element Method
Choon-Yeol Lee, Young-Suk Chai, Jae-Do Kwon, Sang-Tae Kim and Ki-Sang Jang

G01/4

Coupled Thermo-Hydraulic and Elastic-Plastic Analyses of a Cracked Inclined Nozzle
Ph. Gilles, C. Bois, A. Woaye Hune and G. Bezdikian

G01/5

Object-Oriented Probabilistic Finite Element Analysis and its Applications
Jin-Oh Jeong, Chan Cook Park and Uk Youn Cho

G02/1

Development of Hardware-in-the-Loop Simulator for Piping Integrity Evaluation
K J. Kim, J. B. Choi, N S. Huh, C. K Nam and C. R. Pyo

G02/2

Tearing Initiation and Crack Instability Assessments for an Aged Duplex Stainless Steel Pipe under Pressure Loading
B. Michel, C. Poette, M.T. Cabrillat and P. Ledelliou

G02/3

A User-friendly System for Evaluation of Three-Dimensional Stress Intensity Factors
Shinobu Yoshimura, Hideki Kawate, Yoshitaka Wada and Genki Yagawa

G02/4

Comparative Analysis of Defect Assessment Methods Using Fracture Toughness from Small Charpy- V Specimens
Eduardo P. Asta, Francisco A. Cambiasso and Juan J. Balderrama

G02/5

The Fracture Behaviour of the Cast Steel and Its Prediction Using the Local Approach
Valdislav Kozak, Ivo Dlouhy and Miroslav Holzmann

G02/6

BIMET: Structural Integrity of Bi-Metallic Components Program Overview
C. Faidy

G03/1

A Comparison between Japanese and French A16 Assessment Procedures for Fatigue Crack Growth
Takashi Wakai, Christophe Poussard and Bernard Drubay

G03/2

Creep-Fatigue Initiation of a Weldment Joint Singularity in 316L Stainless Steel under Mixed Mode Loading 1 and II
B. Michel, S. Albaladejo, C. Poette, M.T. Cabrillat and B. Martelet

G03/3

A Comparison between Japanese and French A16 Defect Assessment Procedures for Creep-Fatigue Crack Growth
Christophe Poussard, Takashi Wakai and Bernard Drubay

G03/4

Behaviors of Fatigue Crack Initiation and Propagation for Type 316NG Stainless Steel under Multiaxial States of Stress
Satoshi Kanno and Makoto Hayashi

G03/5

Fatigue Crack Propagation and Fatigue Life Prediction under the Mixed Mode Loading
Ouk Sub Lee and Jin Koo Lee

G04/1

Fatigue Crack Growth of Semi-El!iptical Defects in Welded Austenitic Stainless Steel Plates under Bending Loads
Bernard Drubay, Lucien Laiarinandrasana, Pierre Cambefort and Franccois Curtit

G04/2

Implementation of Thermo-Viscoplastic Constitutive Equations into the Finite Element Code
Samson Youn, Soon-Bok Lee, Hyeong-Yeon Lee, Jong-Bum Kim and Bong Yoo

G04/3

Development of Flaw Evaluation Guideline for FBR Components
Naoki Miura, Yasunari Nakayama and Yukio Takahashi

G04/4

The Effect of the Long Term Aging on the Creep Rupture Behavior in Type 316 Stainless Steel
Byeong Soo Lim and Ji Woo Im

G04/5

Surface Crack Growth in Reactor Header Tee under Cyclic Pressure
D. S. Chawla, S. R. Bhate, K. K. Vaze and H. S. Kushwaha

G04/6

Load History Consideration in Regulatory Assessments of Fatigue Crack Growth
Alexadr Vasilyevich Tashkinov

G05/1

Effect of Cladding on Stress Intensity Factors in Reactor Pressure Vessel
Y.J. Kim, J.B. Choi, J.S. Kim, S.N. Choi and K.S. Jang

G05/2 Finite Element Calculation of Stress Intensity Factors for Inlet and Outlet Nozzle Corner Flaws of Pressure Vessel
Choon-Yeol Lee, Il-Sup Chung, Young-Suk Chai, Jae-Do Kwon and Yong-Son Lee

G05/3

Analysis of the Behaviour of an Under-Clad Crack at the Nozzle Corner of a PWR-Pressure-Vessel
S. Bhandari, J. Vagner, D. Guichard and C. Faidy

G05/4

Modelling of Thennaland Flow Stratification for Reactor Pressure Vessel Pressurised Thennal Shock
H.G. Lele, S.K. Gupta, H.S. Kushwaha and V. Venkat Raj

G05/5

Modelling for Ductile-to-Brittle Transition under Ductile Tearing for Reactor Pressure Vessel Steels
Boris Margolin and Viktor Kostylev

G05/6

Activities of the OECD Nuclear Energy Agency in the Area of RPV PTS Fracture Mechanics
Alex G. Miller, Jurgen Sievers and Richard Bass

G06/l

Modeling the Early Development of Secondary Side Stress Corrosion Cracks in Steam Generator Tubes Using Incomplete Random Tessellation
Leon Cizelj and Heinz Riesch-Oppermann

G06/2

Integrity Evaluation of Pressurizer Safety/Relief Nozzle Corner in PWR
Ki Sung Park, Chae Hong Jeon, Yoon Suk Kim, Seung Tae Kim and Warren Bamford

G06/3

A Study on Quantitative Assessment of Crack Tip Constraint by 'Q'Parameter
T.V. Pavankumar, J. Chattopadhyay, B.K. Dutta and H.S. Kushwaha

G06/4

Characterization of Elastic-Plastic Cracks under High Temperature Gradients
H. Yuan, K. Reichlin and D. Kalkhof

G06/5

An Energetic Approach to Simulate 2D Ductile Crack Growth
Stephane Marie and Stephane Chapuliot

G07/l

Plastic Collapse Behavior of Pipe with Local Wall Thinning Subjected to Bending Moment
K. Ando, S.H. Ahn, M. Ishiwata and K. Hasegawa

G07/2 Flaw Evaluation of Japanese Carbon Steel Piping by Load
Koichi Kashima
G07/3

Plastic Collapse and LBB Behavior of Statically Indeterminate Piping System under Static Load
Yeon-Sik Yoo, Hiroaki Shimano, Su-Hwan Ji and Kotoji Ando

G07/4

Limit Load of Elbows under Combined Internal Pressure and Bending Moment
J. Chattopadhyay, W. Venkatramana, B.K. Dutta and H.S. Kushwaha

G07/5

Determination of Maximum Load of TWC Straight Pipes: Comparative Study of Estimation Schemes
M. N Jha, V. Bhasin, K.K. Vaze and H.S. Kushwaha

G08/1

Static and Dynamic J-R Fracture Characteristics of Ferritic Steels for RCS Piping
Bong-Sang Lee, Ji-Hyun Yoon, Yong-Jun Oh, Il-Hiun Kuk and Jun-Hwa Hong

G08/2

A Parametric Study on the Fracture Mechanics Analyses of Through-W: and Surface Cracked Pipe
Hyun-Su Kim, Yoon-Suk Chang and Tae-Eun Jin

G08/3

Structural Integrity Assessment of Pressure Tubes for Wolsung Unit I Based on Operational Experiences
Youn Won Park, Sung Sik Kang and BongSup Han

G08/4

Assessment of Integrity of Elbows in Piping of 5OO MWe PHWR: Using R-6 Method
Rohit Rastogi, Vivek Bhasin, K.K. Vaze and H.S. Kushwaha

G08/5

A Simple Method for Estimating Effective J-Integral in LBB Application to Nuclear Power Plant Piping System
Jun-Seog Yang, Bum-Nyeon Kim, Chi-Yong Park, Young-Seob Park and Ki-Suk Yoon

G08/6

Probabilistic Fracture Analysis of a Straight Pipe with Through-Wall Circumferential Crack Using R6 Method
Rohit Rastogi, Vivek Bhasin, K.K. Vaze, H.S. Kushwaha and Vikas Chandra

G09/1

Circumferential Fatigue Crack Growth and Crack Opening Behavior in Pipes Subjected to Bending Moment
Yeon-Sik Yoo and Kotoji Ando

G09/2

Development of Ceramic Humidity Sensor for the Application of the Leak-Before-Break Concept
Na Young Lee, Il Soon Hwang, Chang Rock Song and Han Il Yoo

G09/3

Leak Rate Through Slits and Cracks in Pipes
B. Ghosh, S.K. Bandyopadhyay, S.K. Gupta, H.S. Kushwaha and V. Venkat Raj

G09/4

Uncertainty of Two-Phase Critical Mass Flux Calculation in Pipes and Slits
K.S. Chang, J.H. Lee and K.W. Seul

G09/5

Welded Joints Corrosion and Mechanical Strength of Piping for Light Water Reactors
Georgy Karzov, Boris Timofeev, Valentina Fedorova, Alexander Gorbakony and Vadim Markov

G10/1

Some Issues by Using the Master Curve Concept
Hans-Werner Viehrig and Juergen Boehmert

G10/2

Estimation of Fracture Toughness in the Transition Region Using CVN Data
Seok Hun Kim, Youn Won Park, Jin Ho Lee and Sung Sik Kang

G10/3

Probabilistic Distribution of Structure Integrity Characteristics of Materials for Russian PWR Reactors
Boris Timofeev, Tatiana Chernaenko and Georgy Karzov

G10/4

U.S. Nuclear Regulatory Commission's Review of the Impact of Inservice Inspection of BWR Reactor Pressure Vessel Welds on Vessel Failure
K
eith Wichman, Barry Elliot and Clarence Carpenter

G10/5

Dynamic Fracture Toughness Test and Master Curve Method Analysis of IAEA JRQ Materials
K.K. Yoon and K. Hour

G10/6

Fracture Toughness Prediction in Probabilistic Statement Based on the New Local Fracture Criteria
Boris Margolin, Alexander Gulenko and Victoria Shvetsova

G11/1

Fracture Toughness of Austenitic Anticorrosive Cladding and Austenitic Welded Joints
Boris Timofeev, Alexander Blumin and Georgy Karzov

G11/2

Fracture and Microstructural Characterization of Type 347 Stainless Steels for Nuclear Primary Piping
Yong Jun Oh, Bong Sang Lee, Ji Hyun Yoon, June Soo Park and Jun Hwa Hong

G11/3

A Fracture Mechanical Behaviour of Aged 15Cr-5Ni Stainless Steel
Kotoji Ando, Atsushi Fuseya, Motoji Tubota and Mincheol Chu

G11/4

Investigation of the Influence of Loading Biaxiality on Fracture Toughness of Pressure Vessel Steels
Viktor Kostylev and Boris Margolin

G11/5

Fracture Toughness of Low Alloyed Steels and Their Welds Determined on Various Criteria and Correction of Normative Approach to Brittle Strength Assessment for Reactor Pressure Vessels
Georgy Karzov, Boris Timofeev, Vladislav Anikovsky and Alexander Blumin

G11/6

Fracture Mechanics Based Assessment of Bimaterial Joints with Interface Cracks
Hyungyil Lee

G12/1 Fracture Mechanics Concepts for Evaluation of Irradiated Reactor Pressure Vessel Material Behavior
K. Kussmaul, J. Fohl and H. Beyer
G12/2

A Study on the Decrease Phenomenon of Fracture Resistance Value under Reversed Cyclic Loading
Chang-Sung Seok, Byoung-Gon Yoon and K. Linga Murty

G12/3

Evaluation of the Fracture Toughness KIC in the Transition Region for Turbine Rotors by Using Charpy Impact Specimen
Jin-Ik Suk and Kook-Chul Kim

G12/4

Estimation of Fracture Mechanical Toughness Through Small Specimen Testing Techniques
Jang-Bog Ju, Baik-Woo Lee, Bong Sang Lee, Jun Hwa Hong and Dongil Kwon

G12/5

Effects of Specimen Thickness and Microstructure on Near-Threshold Fatigue Crack Propagation in Ferritic Steels
Eung Seon Kim and In Sup Kim


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