Developments in fracture mechanics and non-destructive examination

Abstract The purpose of this paper is to give a brief review of the major developments and trends that have occurred in some of the technical areas covered by Division G of SMiRT since the first conference was held in Berlin in 1971. As with any human activity, time and experience produce organic change so that the technical areas covered by Division G have changed somewhat over the 18 years of its existence. As first conceived by Tom Jaeger, Division G was one of two divisions devoted to Light Water Reactor Components other than fuel and cladding. Division F was conceived with Core Structures and Piping whilst Division G was devoted to the Steel Reactor Pressure Vessels.

[1]  G. Volta,et al.  The Research Programme Sponsored by CEA Concerning the Failure Probability Calculation of a PWR Vessel , 1977 .

[2]  Eberhard Roos,et al.  The influence of the material toughness and the state of stress on fracture of large scale specimens , 1987 .

[3]  Kunio Hasegawa,et al.  Stable Growth and Instability of Circumferential Cracks in Type 304 Stainless Steel Pipes Under Tensile Load , 1984 .

[4]  K. Kussmaul.  Mechanics of Materials in Corrosion Assisted Low Cycle Fatigue Crack Growth Analyses , 1987 .

[5]  K. Reading,et al.  A Spinning Cylinder Tensile Test Facility for Pressure Vessel Steels , 1985 .

[6]  I. S. Raju,et al.  Improved Stress-Intensity Factors for Semi-Elliptical Surface Cracks in Finite-Thickness Plates , 1977 .

[7]  F. J. Witt,et al.  The USAEC heavy section steel technology program: Objectives and status , 1972 .

[8]  S. J. Garwood,et al.  Elasto-plastic fracture mechanics applied to the safety assessment of nuclear power stations , 1981 .

[9]  K. Kussmaul,et al.  Some conclusions with regard to the safety assessment of cracked components drawn from the research programme “integrity of components” (FKS II) atthe present state , 1987 .

[10]  K. Kussmaul,et al.  Statistical evaluation of post-yield fracture mechanics properties on the basis of the notched bar impact test , 1985 .

[11]  Satya N. Atluri,et al.  Incremental path-independent integrals in inelastic and dynamic fracture mechanics , 1984 .

[12]  C. de Torquat,et al.  Nuclear Pressure Vessel Analysis According to French Regulations , 1975 .

[13]  R. W Nichols,et al.  Trends in reactor pressure vessel and circuit development , 1980 .

[14]  P. M. Scott,et al.  Stress corrosion in low alloy steels , 1990 .

[15]  C. E. Pugh,et al.  Evaluation of fracture models through pressurized-thermal-shock testing , 1988 .

[16]  Edwin Smith,et al.  An Overview of Crack Arrest as it Applies to Reactor Vessel Integrity , 1979 .

[17]  R. W. Nichols,et al.  Non-destructive examination in relation to structural integrity : proceedings of the 1st International Seminar on 'Non-destructive Examination in Relation to Structural Integrity' held at the International Congress Center Berlin, Berlin (West), Germany, 22nd August 1979, in conjunction with the 5th , 1980 .

[18]  T. Kanazawa,et al.  SOME RECENT TOPICS IN PRESSURE VESSEL TECHNOLOGY , 1989 .

[19]  Genki Yagawa,et al.  Calculation of stress intensity factors of surface cracks in complex structures: Application of efficient computer program EPAS-J1☆☆☆ , 1982 .

[20]  L. H. Larsson.  A calculational round robin in elastic-plastic fracture mechanics , 1983 .

[21]  G. Yagawa,et al.  Determination of Dynamic Fracture Toughness of Nuclear Pressure Vessel Steel Using Electromagnetic Force , 1985 .

[22]  K. Kussmaul,et al.  Enhancement of the quality of the reactor pressure vessel used in light water power plants by advanced material, fabrication and testing technologies , 1980 .

[23]  M. F. Kanninen,et al.  A critical survey on the application of plastic fracture mechanics to nuclear pressure vessels and piping , 1981 .