**9. References**


[11] Berg HP, Hauschild J (2010). Probabilistic assessment of external explosion pressure waves. Proceedings of the 8th International Probabilistic Workshop*,* Szczecin, November 2010, 27 – 39.

150 Nuclear Power – Practical Aspects

*Federal Office for Radiation Protection (BfS),Department of Nuclear Safety, Salzgitter, Germany* 

[1] Shepherd JE (2007) Structural Response to Explosions. 1st European Summer School on

[2] Federal Office for Radiation Protection (Bundesamt für Strahlenschutz – BfS) (2005) Safety Codes and Guides – Translations: Safety Review for Nuclear Power Plants pursuant to § 19a of the Atomic Energy Act - Guide on Probabilistic Safety Analysis.

[3] Facharbeitskreis Probabilistische Sicherheitsanalyse für Kernkraftwerke (FAK PSA) (2005) Methoden zur probabilistischen Sicherheitsanalyse für Kernkraftwerke, Stand: August 2005. BfS-SCHR-37/05, Bundesamt für Strahlenschutz, Salzgitter, Oktober 2005

[4] Facharbeitskreis Probabilistische Sicherheitsanalyse für Kernkraftwerke (FAK PSA) (2005) Daten zur probabilistischen Sicherheitsanalyse für Kernkraftwerke, Stand: August 2005. BfS-SCHR-38/05, Bundesamt für Strahlenschutz, Salzgitter, Oktober 2005

[5] International Atomic Energy Agency (IAEA) (2003) External Events Excluding Earthquakes in the Design of Nuclear Power Plant*,* IAEA Safety Standards Series No.

*[6]* International Atomic Energy Agency (IAEA) (2009) Safety Assessment for Facilities and Activities, General Safety Requirements*.* IAEA Safety Standards Series No. GSR Part 4,

[7] International Atomic Energy Agency (IAEA) (2010) Development and Application of Level 1 Probabilistic Safety Assessment for Nuclear Power Plants. IAEA Safety

[8] International Atomic Energy Agency (IAEA) (2002) External Human Induced Events in Site Evaluation for Nuclear Power Plants, IAEA Safety Standards Series No. NS-G-3.1,

[9] International Atomic Energy Agency (IAEA) (2003) Site evaluation for nuclear installations, Safety Requirements, IAEA Safety Standards Series No. NS-R-3, Vienna,

[10] Hauschild J, Andernacht M. (2010). Monte Carlo simulation for modelling & analysing external explosion event probability. Reliability, Risk and Safety – Back to the Future,

Proceedings of the ESREL Conference 2010, Rhodes, Balkema, 985 – 989.

*TÜV NORD SysTec GmbH & Co. KG, Hamburg, Germany* 

Hydrogen Safety, University of Ulster, August 2007.

Bundesamt für Strahlenschutz, Salzgitter, August 2005.

**Author details** 

Heinz Peter Berg

Jan Hauschild

**9. References** 

(published in German).

(published in German).

Vienna, May 2009.

IAEA, Vienna, May 2002.

November 2003.

NS-G-1.5, Vienna, November 2003.

Standards Series No. SSG-3, Vienna, April 2010.


[26] Lewis EE, Böhm F (1984) Monte Carlo Simulation of Markov Unreliability Models. Nuclear Engineering and Design 77: 49 – 62.

**Chapter 6** 

© 2012 Ahmed, licensee InTech. This is an open access chapter distributed under the terms of the Creative Commons Attribution License (http://creativecommons.org/licenses/by/3.0), which permits unrestricted use,

distribution, and reproduction in any medium, provided the original work is properly cited.

© 2012 Ahmed, licensee InTech. This is a paper distributed under the terms of the Creative Commons Attribution License (http://creativecommons.org/licenses/by/3.0), which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

In general, corrosion is defined as the degradation of a material by means of chemical reactions with the surrounding environment. Several types of corrosion occur in a variety of situations in the nuclear power plants. Some of these types are common such as rusting of steel when located in moist environment, and the other type of corrosion such as flow accelerated corrosion required special treatment due to their impact on the plant safety and reliability. FAC degradation mechanism results in thinning of large areas of piping and fittings that can lead to sudden and sometimes to catastrophic failures, as well as a huge economic loss. FAC is a process caused by the flowing water or wet steam damaging or thinning the protective oxide layer of piping components. The FAC process can be described by two mechanisms: the first mechanism is the soluble iron production (Fe2+) at the oxide/water interface, while the second mechanism is the transfer of the corrosion products to the bulk flow across the diffusion boundary layer. Although the FAC is characterize by a general reduction in the pipe wall thickness for a given piping component, it frequently occurs over a limited area within this component due to the local high area of turbulence. The rate of the metal wall loss due to FAC depends on a complex interaction of several

parameters such as material composition, water chemistry, and hydrodynamic.

i. **Shear stress erosion**: In this category, the surface of a material gets destroyed in singlephase flow at high velocity, by the effects of shear stresses and the variations in the

ii. **Liquid impact induced erosion**: This form of erosion occurs in two-phase flow by the impingement of liquid droplets entrained in flowing gases or vapours. It can cause damages to power plant condenser tubes, elbows, turbine blades, etc. The wear process

In general, erosion processes or mechanisms can be categorized as:

**Flow Accelerated Corrosion** 

Additional information is available at the end of the chapter

**in Nuclear Power Plants** 

Wael H. Ahmed

**1. Introduction** 

fluid velocity.

http://dx.doi.org/10.5772/51346


**Chapter 6** 
