Overview of JSME flaw evaluation code for nuclear power plants

  • Kobayashi H
  • Kashima K
  • 4

    Readers

    Mendeley users who have this article in their library.
  • 12

    Citations

    Citations of this article.

Abstract

A Japanese flaw evaluation code for nuclear power plant components has been developed at the Japan Society of Mechanical Engineers (JSME). The code prescribes methods for the evaluation of flaws, which are detected during inservice inspection for pressure vessels and pipes in nuclear power plants. This paper describes the basic flow chart, methods of evaluation and allowable flaw sizes for acceptance standards and criteria, including comparisons with the ASME Code Section XI. © 2001 Elsevier Science Ltd. All rights reserved.

Author-supplied keywords

  • ASME code
  • Flaw evaluation
  • Fracture mechanics
  • Inservice inspection
  • Nuclear power plant

Get free article suggestions today

Mendeley saves you time finding and organizing research

Sign up here
Already have an account ?Sign in

Find this document

Authors

  • Hideo Kobayashi

  • Koichi Kashima

Cite this document

Choose a citation style from the tabs below

Save time finding and organizing research with Mendeley

Sign up for free