Analysis of the Effect of Pollution of Component Surfaces as a Result of Possible Contact of Fresh Nuclear Fuel with Sea Atmosphere on Corrosion

: pp. 17 – 21
Received: July 20, 2022
Revised: May 22, 2023
Accepted: June 05, 2023

S. Lys. Analysis of the effect of pollution of component surfaces as a result of possible contact of fresh nuclear fuel with sea atmosphere on corrosion. Energy Engineering and Control Systems, 2023, Vol. 9, No. 1, pp. 17 – 21.

Lviv Polytechnic National University

Acquisition and analysis of the information was performed on possible effect of components of sea atmosphere in case of their precipitation on the assembly surfaces on the corrosion of structural materials of items of fuel assemblies (FAs) of water-water energetic reactor (VVER-1000) in their subsequent operation. The data is presented on static and dynamic tests of alloy E-110 at temperatures of 300–350 °С in water and standard coolant of the reactor polluted with chlorides and iodine, as well as of alloy E-110 under special pollution of its surface with chlorides. It is demonstrated that in keeping the conditions of storage of fresh fuel, as well as the recommendations of the present work, its high corrosion resistance and operability in further operation is ensured.

  1. Cox, B. (1973) Stress corrosion of zirconium alloys in neutral chloride. Corrosion. V.29. No.4. p. 157.
  2. Kosinov, V.A., Kuchin, O.P., Novikov, O.K., Osharina, L.V., Fedenko, V.I. (1983) Corrosion of alloy Zr – 1% Nb in distilled water containing ions of Cl or F at temperature 300 °С, IATF specialists meetings on «Influence of water chemistry on fuel element cladding behaviour in water cooled power reactors». Leningrad / USSR/ 6-10 June 1983. /IWGFPT/ 17. IAEA/ Vienna.
  3. Gerasimov, V.V., Gerasimova, V.V. (1989) Chloride and iodide corrosion of zirconium alloys. Pre-print. M., TSNIIatominform. (in Russian)
  4. Knittel, D.R. (1982) The effect of surface treatment on pitting potentials of zirconium in chloride solution. Corrosion. V. 38, No.5, p. 140.
  5. Gerasimov, V.V. (1980) Corrosion of reactor materials., М., Atomizdat. (in Russian)
  6. Migay, L.L., Taritsina, T.A. (1988) Corrosion resistance of materials in halogens and their compounds. M., “Chemistry”. (in Russian)
  7.    Preliminary safety analysis reports. Topical report. Development of recommendations on storage of fresh fuel within five years. Justification of requirements for storage atmosphere, 412-312-О-10, KK.UJA.JKA.TM.TR.PR033, 2001.
  8. Semerak, M.M., Lys, S.S. (2021) Research the behaviour and properties of WWER type fuel claddings from Zr1%Nb alloy in loss of the coolant accident. Problems of atomic science and technology, Kharkiv, No. 2(132). 80–86.
  9. Kalman, I.G. (1971) Effect of environmental factors on hardware and components. Methods of climatic tests. М., “Znanie”. (in Russian)
  10.  Stepan Lys, Alexander Kanyuka (2021) Analysis of fuel rod performance per cycle: Temperature field, FGP release, swelling. Thermal Science and Engineering Progress, Volume 25, 100961.
  11. Stepan  Lys, Alexandr  Kanyuka (2022) Algorithms for processing self-powered neutron detector signals important for determination of local parameters in each part of the VVER core EPJ Nuclear Sci. Technol. 8, 17.
  12. Lys, S.S., Semerak, M.M., Kanyuka, A.I. (2021) Analysis of reliability of automatic core protection function of the reactor V-412 in response to local parameters: maximum linear power, departure from nucleate boiling ratio. Problems of atomic science and technology. Kharkiv, No. 5(135). 88–97.