Paper Titles
Characterisation of Solid Supported Nanostructured Thin Films by Scanning Angle Reflectometry and UV-Vis Spectrometry
p.329
Replacement of Imported Drawn Tubes Built in Heat Exchangers by Longitudinal Seam Pipes Produced by DUNAFERR
p.337
Relationship between the Primary Cast Structure and Distribution of Inclusions in a St52-3 Type Continuously Cast Steel Slab
p.345
Evolution of Special Grain Boundaries in Austenitic Steels
p.355
Effect of Cladding on the Reactor Pressure Vessel Safety
p.363
Temperature Dependence of Barkhausen Noise Parameters in Carbon Steel
p.371
Long-Term Strain Measuring of Technical Textiles by Photographic Method
p.381
Color Etching for Characterization the Grain Orientation in Spheroidal Graphite Cast Iron
p.389
The Effect of Microstructure on the Wear Phenomena
p.397

Effect of Cladding on the Reactor Pressure Vessel Safety

Article Preview

Abstract:

It is common for the most reactor pressure vessel (RPV) of light-water reactors used today, that the RPV made of ferrite-perlitic steel is cladded with an austenitic layer, which well resists corrosion influence. The cladding is manufactured by welding, the technology (mode of application, number of layers) is different by each manufacturer. This is the layer which comes into contact with the working media first, and is of course in cohesive contact with the RPV material. The aim of this study is to demonstrate the new approach, used for assessing the safety of the reactors today. This approach plays a decisive role in the lifespan calculation of already operating nuclear power stations, including the extension of their service period.

You might also be interested in these eBooks
Materials Science, Testing and Informatics III View Preview

Info:

Periodical:

Materials Science Forum (Volumes 537-538)

Pages:

363-370

DOI:

https://doi.org/10.4028/www.scientific.net/MSF.537-538.363

Citation:

Cite this paper

Online since:

February 2007

Authors:

György András Gémes

Keywords:

Energetic, Extension Operational Lifetime, Reactor Safety

Export:

RIS, BibTeX

Price:

Permissions CCC:

Request Permissions

Permissions PLS:

Request Permissions

Сopyright:

© 2007 Trans Tech Publications Ltd. All Rights Reserved

Share:

Citation:

References

[1] Validation of neutron embrittlement for VVER 1000 & 440/312 RPVs, with emphasis on integrity assessment (TAREG 2. 01/00 Technical Report, JRC Petten, 2004), p.10.

DOI: 10.1016/j.pnucene.2012.02.007

Google Scholar

[2] F.M. Haggag and R.K. Nanstad: Effects of Thermal Ageing and Neutron Irradiation on the Mechanical Properties of Three-Wire Stainless Steel Weld Overlay Cladding, (ORNL Report NUREG/CR-6363 and ORNL/TM-13047, 1997), p.85.

DOI: 10.2172/477676

Google Scholar