Published 1987 | Version v1
Journal article

Review of fracture toughness requirements and data relevant to LWR reactor pressure vessels

  • 1. UKAEA Risley Nuclear Power Development Establishment

Description

A survey of current code requirements (ASME and RCC-M) relating to the fracture toughness properties of the ferritic materials used in the fabrication of PWR reactor pressure vessels is presented, together with supporting test data published in the period 1970 to 1985. These fracture toughness properties are discussed in relation to the critical sizes of defect applicable to particular regions of a PWR primary vessel for given design basis transient conditions. (author)

Additional details

Publishing Information

Journal Title
Int. J. Press. Vessels Piping
Journal Volume
29
Journal Issue
5
Series
Int. J. Press. Vessels Piping.
Journal Page Range
343-428
ISSN
0308-0161
CODEN
PRVPA