Ваш браузер устарел.

Для того, чтобы использовать все возможности сайта, загрузите и установите один из этих браузеров.

скрыть

Article

  • Title

    PREDICTION OF OPERATION LIFE EXTENSION OF HEAT POWER EQUIPMENT

  • Authors

    Skalozubov V.
    Alali M.
    Pirkovskiy D.
    Algerby R.

  • Subject

    ENERGETICS. HEAT ENGINEERING. ELECTRICAL ENGINEERING

  • Year 2020
    Issue 2(61)
    UDC 629.031
    DOI 10.15276/opu.2.61.2020.06
    Pages 51-60
  • Abstract

     Based on the analysis of known researches, it is revealed that the quantity and accumulation rate of cyclic thermal and dynamic loads in the transient modes of normal operation conditions, when violating normal operation conditions and in accident conditions (except for the nuclear reactor vessel) are the key factors of prediction of operation life extension for a heat power equipment (heat exchangers, pumps, armature). The method for predictive estimation of terms of operation life extension of a heat power equipment depending on stress amplitudes in transient and accident conditions, quantity and accumulation rate of cyclic loads, strength metal parameters of a heat power equipment vessels (except for a reactor vessel) is provided. The method is implemented on the example of steam generators of WWERs and using operational data of South-Ukraine-1 (by 2010). Admissible accumulation rate of cyclic loads during operation life extension by 30, 40 and 50 years is a result. The results define insufficient substantiation of nuclear power plant operation in the “maneuverable” modes with a variable reactor power. In this case, the quantity of cyclic equipment loads increases dramatically, and terms of safe operation are limited. The developed method and the obtained results of prediction of operation life extension of heat power equipment can be used for industry programs to extend the operation of Ukrainian nuclear power plants, as well as to improve the regulatory documents governing the conditions and requirements for acceptable safe extension of the operation life of heat power equipment of nuclear and thermal power enterprises. Further improvement of the method proposed in the work for predicting operation life extension of heat power equipment can be based on the development of methods for analyzing the reliability of heat power equipment and databases on operation disturbances.The materials of the presented work are used in the educational process for the training, retraining and advanced training of specialists in the energy industry.

  • Keywords prediction, operation life extension, heat power equipment
  • Viewed: 40 Dowloaded: 1
  • Download Article
  • References

    Література

    1.Острейковский В.А. Старение и прогнозирование ресурса оборудования атомных станций. М. : Энергоатомиздат, 1994. 287 с.

    2.Kossilov A. IAEA Co-ordinated Research Programme on Management of Ageing of Motor Operated Isolating Valves. Proceeding of the Joint Specialist Meeting on Motor Operated Valve Issues in Nuclear Power Plants, Paris, France, 1994, April 25–27. 1994. Р. 369–383.

    3.Гетман А.Ф. Концепция безопасности «течь перед разрушением» для сосудов и трубопроводов давления АЭС. М. : Энергоатомиздат, 1999. 258 с.

    4.Зарицкий Н.С., Лагута С.М., Седнев В.А. Скалозубов В.И. Анализ отказов арматуры энергобло-ков Запорожской АЭС. Ядерная и радиационная безопасность. 2000. 2. С. 86–89.

    5.Зарицкий Н.С., Седнев В.А. Скалозубов В.И. Анализ эксплуатационных данных по дефектам те-плообменных труб парогенераторов ВВЭР. Ядерная и радиационная безопасность. 2000. 1. С. 96–98.

    6.Повышение динамической надежности и продление срока службы трубопроводов при использо-вании технологии высоковязкого демпфера / В.В. Костарев, Д.Ю. Павлов, В.Н. Алексеев, А.М. Берковский, А.Ю. Щукин. Тяжелое машиностроение. 2000. 8. С. 26–33.

    7.РД ЭО 0185-00. Методика оценки технического состояния и остаточного ресурса трубопроводов энергоблоков АЭС. М. : Росэнергоатом, 2000. 73 с.

    8.ПН АЭ Г-7-002-86. Нормы расчета на прочность оборудования и трубопроводов атомных энер-гетических установок. М. : Энергоатомиздат, 1999. 525 с.

    References

    1.Ostreykovsky, V.A. (1994). Ageing and Resource Prediction of Equipment of Nuclear Power Plants. Moscow: Energoatomizdat.

    2.Kossilov, A. (1994). IAEA Co-ordinated Research Programme on the Management of Ageing of Motor Operated Isolating Valves. Proceeding of the Joint Specialist Meeting on Motor Operated Valve Issues in Nuclear Power Plants, Paris, France, April 25-27, 369–383.

    3.Getman, А.F. (1999). Safety Concept “Leak before Break” for NPP Pressure Vessels and Pipelines. Moscow: Energoatomizdat.

    4.Zaritsky, N.S., Laguta, S.М., Sednev, V.A. & Skalozubov, V.I. (2000). Analysis of Armature Failures at Zaporizhzhya Power Units. Nuclear & Radiation Safety, 2, 86–89.

    5.Zaritsky, N.S., Sednev, V.A., & Skalozubov, V.I. (2000). Analysis of Operational Data on Defects in Heat Exchanger Tubes of WWER Steam Generators. Nuclear & Radiation Safety, 1, 96–98.

    6.Kostarev, V.V., Pavlov, D.J., Аlekseev, V.N., Berkovski, А.М., & Shukin, A.J. (2000). Improving Dy-namic Reliability and Extending the Operation Life of Pipelines Using High Viscous Damper Technol-ogy. Russian Journal of Heavy Machinery (Tyazheloe mashinostroenie), 8, 26–33.

    7.RD EО 0185-00. Methodology for Assessing the Technical Condition and Residual Life of Pipelines of Nuclear Power Units (2000). Moscow: Rosenergoatom, 73.

    8.PN AE G-7-002-86. Codes of Strength Design for Equipment and Pipelines at Nuclear Power Plants (1989). Moscow: Energoatomizdat, 525.

  • Creative Commons License by Author(s)