A Japanese flaw evaluation code for nuclear power plant components has been
developed at: the Japan Society of Mechanical Engineers (JSME). The code p
rescribes methods for the evaluation of flaws, which are detected during in
service inspection for pressure vessels and pipes in nuclear power plants.
This paper describes the basic dow chart, methods of evaluation and allowab
le flaw sizes for acceptance standards and criteria, including comparisons
with the ASME Code Section XI. (C) 2001 Elsevier Science Ltd. All rights re
served.