Corrosion surveillance program for tank, fuel cladding and supporting structure of 30 MW Indonesian RSG GAS research reactor
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G. R. Sunaryo
,
R. Kusumastuti
Abstract
The objective of this research is to understand the condition of the structural material of the 30 MW RSG-GAS research reactor as input for the aging management program. Furthermore, this should enable a prediction of the remaining life of the components. In the current experiment, corrosion surveillance was carried out at Interim Storage for Spent Fuel (ISSF), that has similar water quality as in reactor pool by using a corrosion probe which is made of aluminum alloy and stainless steel. The probe set is designed to understand the effect of water quality in the ISSF pond. The corrosion processes observed were pitting, crevice and galvanic corrosion. Two sets of corrosion probes were immersed into the ISSF pool in 2007, hanging by steel wire, 1-meter height from the bottom surface. One probe set consists of horizontal and vertical positions. The soaking time was 7 years. The observations made were water chemical content, corrosion rate and visual analysis, macro and micro. For macro visual observations an optical microscope was used, for micro-observations SEM-EDX. From the results of macro-observations, information on the presence of galvanic corrosion, crevice and pitting was obtained. SEM-EDX provides information on the influence of chloride ions on corrosion products. This experience will be very useful in dealing with the aging process of Indonesia’s nuclear power plants in the future.
Abstract
Das Ziel dieser Forschung ist es, für das Programm zum Alterungsmanagement den Zustand des Strukturmaterials des 30 MW RSG-GAS-Forschungsreaktors zu verstehen. Des Weiteren soll damit eine Vorhersage der Restlebensdauer der Komponenten möglich werden.
Im aktuellen Experiment wurde die Korrosionsüberwachung im Zwischenlager für abgebrannte Brennstoffe (ISSF) durchgeführt, das eine ähnliche Wasserqualität wie das Reaktorbecken hat. Die dazu verwendete Probe besteht aus einer Aluminiumlegierung und rostfreiem Stahl und wurde entwickelt, um die Auswirkungen der Wasserqualität im ISSF-Becken zu verstehen. Die beobachteten Korrosionsprozesse waren Lochfraß, Spaltkorrosion und galvanische Korrosion. Insgesamt wurden zwei Korrosionsproben im Jahr 2007 in das ISSF-Becken eingetaucht. Sie hingen an einem Stahldraht 1 m oberhalb des Bodens. Ein Probenset enthält horizontale und vertikale Positionen. Die gesamte Eintauchzeit der Proben betrug 7 Jahre. Als Ergebnis wurden der chemische Wassergehalt und die Korrosionsrate gemessen und es erfolgte eine visuelle Makroanalyse mit einem optischen Mikroskop und eine visuelle Mikroanalyse mit Hilfe SEM-EDX. Aus den Ergebnissen der Makrobeobachtungen wurden Informationen über das Vorhandensein von galvanischer Korrosion, Spalt- und Lochfraß gewonnen. SEM-EDX liefert Informationen über den Einfluss von Chlorid-Ionen auf die Korrosionsprodukte. Diese Ergebnisse werden für den zukünftigen Umgang mit dem Alterungsprozess der indonesischen Kernkraftwerke genutzt.
Acknowledgements
The author appreciates gratefully acknowledge to Batan, Center for Nuclear Reactor Technology and Safety, for the financial support, that makes this research possible. Some of the budget for experiment was taken privately, as well.
References
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© 2021 Walter de Gruyter GmbH, Berlin/Boston, Germany
Artikel in diesem Heft
- Frontmatter
- Study of PWR hot leg creep rupture and RCS depressurization strategy during an SBO accident
- Effect of gap design pressure on the LWR fuel rods lifetime
- Simulation of turbulent mixing rate in simulated subchannels of a reactor rod bundle
- Methodology for analyzing accidents with radioactive material release with code EPZDose
- Development and usage of the digital SAMG system
- Analysis of Doppler reactivity of SMART reactor core for hybrid fuel configurations of UO2, MOX and (Th/U)O2 using OpenMC
- Corrosion surveillance program for tank, fuel cladding and supporting structure of 30 MW Indonesian RSG GAS research reactor
- Investigation of effects of nonavailability of passive safety systems on the reactor behaviour during LOCA Scenario in AP600
Artikel in diesem Heft
- Frontmatter
- Study of PWR hot leg creep rupture and RCS depressurization strategy during an SBO accident
- Effect of gap design pressure on the LWR fuel rods lifetime
- Simulation of turbulent mixing rate in simulated subchannels of a reactor rod bundle
- Methodology for analyzing accidents with radioactive material release with code EPZDose
- Development and usage of the digital SAMG system
- Analysis of Doppler reactivity of SMART reactor core for hybrid fuel configurations of UO2, MOX and (Th/U)O2 using OpenMC
- Corrosion surveillance program for tank, fuel cladding and supporting structure of 30 MW Indonesian RSG GAS research reactor
- Investigation of effects of nonavailability of passive safety systems on the reactor behaviour during LOCA Scenario in AP600
