NESC-IV Project: an Investigation of the Transferability of Master Curve Technology to Shallow Flaws in Reactor Pressure Vessel Applications - Final Report

The NESC– IV project addressed the transferability of fracture toughness data from laboratory specimens to applications that assess the integrity of reactor pressure vessels subjected to upset and normal loading transients. The main focus was six biaxial bend cruciform tests of surface-breaking semi-elliptic defects in a reactor pressure vessel longitudinal weld and four uniaxial tests on extended sub-clad defects in adjacent plate material. The experimental/analytical program drew from major elements of the US Heavy Steel Technology Program. Extensive materials testing and fracture analyses were performed by 20 European organisations, coordinated by the Network for Evaluating Structural Components (NESC). The mission of the Joint Research Centre is to provide customer-driven scientific and technical support for the conception, development, implementation and monitoring of EU policies. As a service of the European Commission, the JRC functions as a reference centre of science and technology for the Union. Close to the policy-making process, it serves the common interest of the Member States, while being independent of special interests, whether private or national.

[1]  Philip Minnebo,et al.  Analysis of fracture tests on large bend beams containing an embedded flaw , 2006 .

[2]  V. I. Kostylev,et al.  Analysis of biaxial loading effect on fracture toughness of reactor pressure vessel steels , 1998 .

[3]  N. Taylor,et al.  Nesc Benchmark Tests to Support Improved Structural Integrity Assessment (G055) , 2003 .

[4]  C. Shih,et al.  Family of crack-tip fields characterized by a triaxiality parameter—I. Structure of fields , 1991 .

[5]  Kim Wallin,et al.  Quantifying Tstress controlled constraint by the master curve transition temperature T0 , 2001 .

[6]  J. W. Bryson,et al.  Biaxial loading and shallow-flaw effects on crack-tip constraint and fracture toughness , 1994 .

[7]  Andrew H. Sherry,et al.  COMPENDIUM OF T‐STRESS SOLUTIONS FOR TWO AND THREE DIMENSIONAL CRACKED GEOMETRIES , 1995 .

[8]  Kim Wallin.  Use of the Master Curve methodology for real three dimensional cracks , 2007 .

[9]  J. W. Bryson,et al.  Initial results of the influence of biaxial loading on fracture toughness , 1993 .

[10]  U. Chatterjee,et al.  Effect of unconventional feeds on production cost, growth performance and expression of quantitative genes in growing pigs , 2022, Journal of the Indonesian Tropical Animal Agriculture.

[11]  Paul T. Williams,et al.  Effect of Shallow Flaws and Biaxial Loading on Transition Temperatures Using a Weibull Stress Model , 2004 .

[12]  W. E. Pennell,et al.  Fracture assessment of shallow-flaw cruciform beams tested under uniaxial and biaxial loading conditions , 1999 .

[13]  C. Shih,et al.  Family of crack-tip fields characterized by a triaxiality parameter—II. Fracture applications , 1992 .

[14]  David Lidbury.  Validation of Constraint Based Methodology in Structural Integrity: Project Overview and Update , 2004 .

[15]  Michael Smith.  Constraint-based R6 assessments of NESC-4 uniaxial beam tests , 2004 .

[16]  Taylor Nigel,et al.  Improving Structural Integrity Assessment Techniques , 2005 .

[17]  J. W. Bryson,et al.  Development of a methodology for the assessment of shallow-flaw fracture in nuclear reactor pressure vessels: Generation of biaxial shallow-flaw fracture toughness data , 1998 .

[18]  C. E. Pugh,et al.  DEVELOPMENT OF A WEIBULL MODEL OF CLEAVAGE FRACTURE TOUGHNESS FOR SHALLOW FLAWS IN REACTOR PRESSURE VESSEL MATERIAL , 2005 .

[19]  Andrew H. Sherry,et al.  Engineering Assessment of Constraint Effects on Cleavage Fracture , 2004 .

[20]  Iradj Sattari-Far.  Study on Fracture Behaviour in Clad Cruciform Specimens under Biaxial Loading (G075) , 2003 .

[21]  A. Pineau,et al.  A local criterion for cleavage fracture of a nuclear pressure vessel steel , 1983 .

[22]  J. W. Bryson,et al.  Biaxial loading effects on fracture toughness of reactor pressure vessel steel , 1995 .

[23]  J D G Sumpter,et al.  Constraint based analysis of shallow cracks in mild steel , 1992 .

[24]  B. R. Bass,et al.  Application of the Weibull Methodology to a Shallow-Flaw Cruciform Bend Specimen Tested Under Biaxial Loading Conditions , 2000 .

[25]  J. W. Bryson,et al.  An Investigation of Cladding Effects on Shallow-Flaw Fracture Toughness of Reactor Pressure Vessel Steel Under Prototypic Biaxial Loading , 1999 .

[26]  Paul T. Williams,et al.  Application of a Weibull Stress Model to Predict the Failure of Surface and Embedded Cracks in Large Scale Beams Made of Clad and Unclad RPV Steel , 2004 .

[27]  Claudio Ruggieri,et al.  Calibration of Weibull stress parameters using fracture toughness data , 1998 .

[28]  Paul T. Williams,et al.  Evaluation of constraint methodologies applied to a shallow-flaw cruciform bend specimen tested under biaxial loading conditions , 1998 .

[29]  S. Esterby.  American Society for Testing and Materials , 2006 .

[30]  Nilsson Karl-Fredrik,et al.  NESC-II Final Report: Brittle Crack Initiation, Propagation and Arrest of Shallow Cracks in a Clad Vessel under PTS Loading. , 2003 .

[31]  John G. Merkle,et al.  Preliminary assessment of the effects of biaxial loading on reactor pressure vessel structural-integrity-assessment technology , 1996 .