Published July 2005 | Version v1
Book

Neutron irradiation embrittlement modeling in RPV steels--an overview

  • 1. School of Materials Sceince and Engineering, Beijing Univ. of Aeronautics and Astronautics, Beijing (China)

Description

The degradation of reactor pressure vessel (RPV) steels due to neutron irradiation embrittlement is of particular concern because of its relevance to plant safety and limitation of plant life. In order to ensure structural integrity and safe operation of the nuclear power plant (NPP), it is essential to understand the damage mechanisms in RPV steels and their effect on mechanical behavior of material. To account for the synergistic effects of various embrittlement variables, both microscale and atomic scale models are being successfully used for assessment of structural integrity of RPV. This paper encompasses a brief description of microstructural effects of irradiation in RPV steels resulting in ductile to brittle transition temperature (DBTT) and reduction of fracture toughness, followed by an overview of the existing damage mechanism models. Besides a brief description of the fracture mechanics concept to the irradiation embrittlement, salient features of major damage mechanism models along with the future scope of further developments have been discussed. (authors)

Part of:
Proceedings of 18th international conference on structural mechanics in reactor technology

Additional details

Publishing Information

Publisher
Atomic Energy Press
Imprint Place
Beijing (China)
ISBN
7-5022-3421-7
Imprint Title
Proceedings of 18th international conference on structural mechanics in reactor technology
Imprint Pagination
4896 p.
Journal Page Range
p. 1015-1025

Conference

Title
18. international conference on structural mechanics in reactor technology
Dates
7-12 Aug 2005
Place
Beijing (China)

Optional Information

Notes
4 figs., 1 tab., 55 refs.