

Operational monitoring of the metal of solution pressure vessel reactors at NRC “Kurchatov institute”
https://doi.org/10.22349/1994-6716-2022-112-4-191-198
Abstract
The paper considers experience of using witness samples for monitoring the state of the metal of the Argus reactor pressure vessel with fuel in the form of an aqueous solution of uranyl sulfate at a nuclear facility at the National Research Center “Kurchatov Institute”. Tests for resistance to intergranular corrosion were carried out in order to establish the actual state of the material. The main objective of the research was to identify corrosion defects. The approach involves the study of witness samples made of steel grade 08Kh18H10T, interconnected by welding wire St 04Kh19H11M3. Witness samples are examined. Extraction of samples for analysis is carried out approximately once every 10 years, or when an energy release (more than 5‧105 kWh) is reached. The high resistance of the materials used in the corrosive environment of the fuel solution is shown on the basis of experimental results.
About the Authors
T. V. BoikovaRussian Federation
123182 Moscow, Sq. Academician Kurchatov, 1
Y. O. Kochnov
Russian Federation
123182 Moscow, Sq. Academician Kurchatov, 1
S. V. Myasnikov
Russian Federation
123182 Moscow, Sq. Academician Kurchatov, 1
N. V. Petrunin
Russian Federation
123182 Moscow, Sq. Academician Kurchatov, 1
S. S. Terashkevich
Russian Federation
123182 Moscow, Sq. Academician Kurchatov, 1
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Review
For citations:
Boikova T.V., Kochnov Y.O., Myasnikov S.V., Petrunin N.V., Terashkevich S.S. Operational monitoring of the metal of solution pressure vessel reactors at NRC “Kurchatov institute”. Voprosy Materialovedeniya. 2022;(4(112)):191-198. (In Russ.) https://doi.org/10.22349/1994-6716-2022-112-4-191-198