Analysis of Efficiency of Technical Condition of Heat Exchanger of Spent Fuel Pool Cooling System with WWER-1000 Reactor of Nuclear Power Plant

2022;
: pp. 65 – 72
https://doi.org/10.23939/jeecs2022.02.065
Received: October 03, 2022
Revised: November 08, 2022
Accepted: November 15, 2022

T. Kovalenko, V. Serdiuk. Analysis of efficiency of technical condition of heat exchanger of spent fuel pool cooling system with WWER-1000 reactor of nuclear power plant. Energy Engineering and Control Systems, 2022, Vol. 8, No. 2, pp. 65 – 72. https://doi.org/10.23939/jeecs2022.02.065

1
Lviv Polytechnic National University
2
Mayo Clinic

The main factors affecting the elements of the heat exchanger of the spent fuel pool cooling system during operation are considered. The analysis of design, technical and operational documentation is carried out for the purpose of preliminary assessment of the technical condition of the heat exchange equipment of nuclear power plants. The data on the installed capacity and service life of power units of the Ukrainian NPPs are given. The cooling system of the spent fuel pool with the WWER-1000 reactor, its purpose, as well as the technical characteristics of the system heat exchanger and its schematic representation are described. The potential mechanisms of aging of heat exchanger elements, aging effects, parameters of technical condition and methods of their control are determined. The efficiency of the heat exchanger of the spent fuel pool cooling system is calculated by determining the rating and design heat transfer areas. The influence of the service life of the heat exchanger on the change in the heat transfer area is shown and the assessment of the effective use of the heat transfer area is determined. The main rating parameters are summarized in the table and the analysis of these values is carried out.

  1. PL-D.0.03.126-10. Regulations on the procedure for extending the service life of equipment of safety-critical systems / Energoatom SE NNEGC. ‒ Kyiv: Energoatom, 2010. ‒ 30 p. – Regulatory document. (in Ukrainian)
  2. PM-D.0.03.222-14. Typical program for managing the aging of elements and structures of a NPP power unit / Energoatom SE NNEGC. ‒ Kyiv: Energoatom, 2014. ‒ 60 p. (in Ukrainian)
  3. Kovalenko, T., Lys, S., Vostres, V. Analysis of eddy-current testing and metallographic examinations for corrosion damages of heat exchanging tubes in NPP steam generators. Energy Engineering and Control Systems, 2020, Vol. 6, No.1, pp. 7–15. https://doi.org/10.23939/jeecs2020.01.007.
  4. Shugailo, Ol-y.P., Grebenyiuk, Yu.P., Zelenyi, O.V., Ryzhov, D.І., Shugailo, Ol-r.P., Brik, D.S., Cherniak, Y.P. (2020). Experience gained and lessons learnt regarding the transition of power units of the NPPs of Ukraine to long-term operation. Nuclear and radiation safety, 1(85), pp. 15-28. https://doi.org/10.32918/nrs.2020.1(85).02. (in Ukrainian)
  5. Scientific work 306.2.141-2008. General safety provisions of nuclear power plants / State Nuclear Regulatory Inspectorate of Ukraine. ‒ Official publication. ‒ Kyiv: State Nuclear Regulatory Inspectorate of Ukraine, 2008. ‒ 61 p. ‒ Regulatory document. (in Ukrainian)
  6. Shugailo, O.P., Plachkov, H.I., Grebenyuk, Yu.P., Shevchenko, І.А., Dybach, О.М., Zelenyi, O.V., Moskalyshyn, R. І. (2018). The main results of analysis of the state of aging management of nuclear power plants in Ukraine. Nuclear and radiation safety, 3(79), pp. 3-9. https://doi.org/10.32918/nrs.2018.3(79).01. (in Ukrainian)
  7. Cherniak, Y.P, Shugailo, O-i.P., Brik, D.S С., Kuznetsova, Kh.V., Demeshko, V.О. (2021). Generalization of results of the assessment of the technical condition and extension of life of the parts of the main seal of the WWER-1000 reactor of power units No. 1 - 4 of KhNPP Separate Subdivision. Nuclear and radiation safety, 1(89), pp. 36-48. https://doi.org/10.32918/nrs.2021.1(89).05. (in Ukrainian)
  8. Shugailo, O.P., Ligotskyy, О.І., Pecherytsia, О.V., Kulman, О.М., Moskalyshyn, R І., Khalenko, R.V., Kurman,  О.М. (2020). Results of the analysis of aging related events at the Ukrainian NPPs. Nuclear and radiation safety, 2(86), pp. 44-51. https://doi.org/10.32918/nrs.2020.2(86).06. (in Ukrainian)
  9. V.І. Konshyn, M.S. Zaiats Assessment of the technical condition of the emergency cooling heat exchanger for the V-320 reactor unit with the aim of extending its life. Bulletin of the National Technical University "Kharkiv Polytechnic Institute". Series: Energy and heat engineering processes and equipment, No. 3(7), 2021, pp. 36-43.  https://doi.org/10.20998/2078-774X.2021.03.05. (in Ukrainian)
  10. PМ-Т.0.08.163-05. Typical program for assessing the technical condition and reassigning the resource/service life of vessels / Energoatom SE NNEGC. ‒ Kyiv: Energoatom, 2003. ‒ 234 p. (in Ukrainian)
  11. 08.8111.333 OI. Heat exchanger operating instructions / Energoatom SE NNEGC. ‒ Kyiv: Energoatom, 2005. ‒ 53 p. (in Ukrainian)
  12. Standard of the Organization of Ukraine NNEGC 080:2014. Operation of a technological complex. Long-term operation of existing NPP power units. General provisions. (in Ukrainian)
  13. Standard of the Organization of Ukraine NNEGC 109:2016. Operation of a technological complex. Monitoring of NPP engineering structures. General provisions. (in Ukrainian)
  14. МТ-D.0.03.391-09. Methods for assessing the strength and service life of WWER reactor vessels during operation. (in Russian)