Abstract
With the increasing age of nuclear power plants, stainless steel core components suffer from increasing irradiation damage. Cracking in such core components occurs due to a combination of high temperature, stress and irradiation, and is strongly affected by the corrosion potential. The corrosion potential is a useful measure for monitoring of cracking as it can help to identify when it is likely to occur (high value of the corrosion potential) and when it is not likely to occur (low value of the corrosion potential). For example, irradiation-assisted stress corrosion cracking (IASCC) has been observed in both boiling water reactors (BWRs) and pressurized water reactors (PWRs) [1, 2]. The corrosion potential is used for monitoring and mitigating IASCC, since IASCC of stainless steels in BWRs can be prevented if the corrosion potential is decreased below −230 mV (standard hydrogen electrode, SHE) [3]. IASCC occurs above a threshold fast neutron dose which depends on the reactor type (BWR vs PWR). To measure the corrosion potential a reference electrode is needed.
Original language | English |
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Title of host publication | Electrochemistry in Light Water Reactors |
Subtitle of host publication | Reference Electrodes, Measurement, Corrosion and Tribocorrosion Issues |
Publisher | WP - Woodhead Publishing |
Chapter | 2 |
Pages | 43-72 |
Number of pages | 30 |
ISBN (Print) | 9781845692407 |
DOIs | |
State | Published - Apr 2007 |
ASJC Scopus subject areas
- General Engineering