0
RESEARCH PAPERS

Fracture Safety Analysis Concepts for Nuclear Pressure Vessels, Considering the Effects of Irradiation

[+] Author and Article Information
J. G. Merkle

Oak Ridge National Laboratory, Oak Ridge, Tenn.

J. Basic Eng 93(2), 265-273 (Jun 01, 1971) (9 pages) doi:10.1115/1.3425223 History: Received July 30, 1970; Online October 27, 2010

Abstract

One of the most important aspects of the growth of nuclear power has been the development and use of quantitative methods of analysis for insuring the reliability of plant components and for protecting the public health and safety. Nuclear pressure vessels have always received close attention with regard to their structural strength and reliability. This paper summarizes some of the fracture mechanics concepts now being considered for application to the safety analysis of nuclear pressure vessels. The effects of thickness, temperature, strain rate, and irradiation on fracture toughness are discussed in terms of their relevance to a safety analysis. The amount of neutron irradiation likely to be received by a light water reactor pressure vessel is examined in terms of reactor type and the thermal power level. The ranges of temperature and fluence that are of most importance with regard to irradiation effects data on pressure vessel steels are identified. An example safety analysis problem is included to illustrate the application of the concepts discussed.

Copyright © 1971 by ASME
Your Session has timed out. Please sign back in to continue.

References

Figures

Tables

Errata

Discussions

Some tools below are only available to our subscribers or users with an online account.

Related Content

Customize your page view by dragging and repositioning the boxes below.

Related Journal Articles
Related eBook Content
Topic Collections

Sorry! You do not have access to this content. For assistance or to subscribe, please contact us:

  • TELEPHONE: 1-800-843-2763 (Toll-free in the USA)
  • EMAIL: asmedigitalcollection@asme.org
Sign In