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ASTM STP 1418 Small Specimen Test Techniques: Fourth Volume

ASTM STP 1418 is offered by IHS as part of an online subscription to the Special Technical Publications Library.

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Sokolov MA

This STP, Small Specimen Test Techniques: Fourth Volume, contains papers presented at the symposium of the same name held in Reno, Nevada on 23-25 January, 2000. The symposium was sponsored by the ASTM International Committee El0 on Nuclear Technology and Applications.

The papers in this publication are divided into sections that correspond to presentation sessions on the following topics: Fracture Toughness, Small Size Charpy V-notch Specimens, Mechanical Properties, Small Punch Tests, and Reconstitution Techniques. Specific topics covered by the papers in this collection include:

  • RPV (Reactor Pressure Vessel) embrittlement
  • Finite element simulation
  • correlation between subsize and full-size Charpy impact properties
  • ductile-to-brittle transition temperature (DBTT)
  • upper shelf energy (USE)
  • specimen reconstitution
  • fracture toughness testing
  • elastic-plastic temperature range
  • fatigue test techniques for irradiated specimens
  • Zircaloy cladding
  • low activation ferritic steel
  • continuum constitutive laws
  • J-incremental flow plasticity theory
  • test specimen design
  • disk bend test
  • deformation mechanisms
  • irradiation effects
  • 316LN stainless steel
  • ion-irradiated TEM disks
  • electrochemical polishing
  • plastic deformation maps
  • miniaturized Cracked Round Bar (MCRB)
  • effect of test machine compliance
  • Ramberg-Osgood Relation
  • shear punch test
  • RESQUE
  • CO laser welding
  • impact testing
  • pre-cracked Charpy specimen

This STP provides readers ideas and techniques for extracting mechanical property information from relatively small volume specimens. This information is useful for engineers, researchers, and other technical professionals interested in effectively using limited volumes of material for irradiation experiments for the development of fusion reactor materials, as well as those needing to improve the information obtainable from specimens in existing light water power reactor surveillance programs and non-nuclear applications.