Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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The information system concept for thermal monitoring of a spent nuclear fuel storage container

  • Received : 2023.04.06
  • Accepted : 2023.07.03
  • Published : 2023.10.25
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Abstract

The paper notes that the most common way of handling spent nuclear fuel (SNF) of power reactors is its temporary long-term dry storage. At the same time, the operation of the dry spent fuel storage facilities almost never use the modern capabilities of information systems in safety control and collecting information for the next studies under implementation of aging management programs. The author proposes a structure of an information system that can be implemented in a dry spent fuel storage facility with ventilated storage containers. To control the thermal component of spent fuel storage safety, a database structure has been developed, which contains 5 tables. An algorithm for monitoring the thermal state of spent fuel was created for the proposed information system, which is based on the comparison of measured and forecast values of the safety criterion, in which the level of heating the ventilation air temperature was chosen. Predictive values of the safety criterion are obtained on the basis of previously published studies. The proposed algorithm is an implementation of the information function of the system. The proposed information system can be used for effective thermal monitoring and collecting information for the next studies under the implementation of aging management programs for spent fuel storage equipment, permanent control of spent fuel storage safety, staff training, etc.

Keywords

Acknowledgement

This work was carried out under partial support of the Non-Residential Fellowship Program "Universities for Ukraine (U4U)".

References

  1. J. Kim, S. Lee, P.H. Seong, Autonomous Nuclear Power Plants with Artificial Intelligence, Springer International Publishing, Cham, 2023.
  2. W. Hoffelner, Materials for Nuclear Plants: from Safe Design to Residual Life Assessments, 2013, pp. 1-478, https://doi.org/10.1007/978-1-4471-2915-8.
  3. P.G. Tipping, Understanding and Mitigating Ageing in Nuclear Power Plants: Materials and Operational Aspects of Plant Life Management (PLIM), Elsevier, 2010.
  4. O.K. Chopra, D.R. Diercks, R.R. Fabian, Z.H. Han, Y.Y. Liu, Managing Aging Effects on Dry Cask Storage Systems for Extended Long-Term Storage and Transportation of Used Fuel (REV. 2) (No. ANL-13/15), Argonne National Lab.(ANL), 2014.
  5. Ageing Management and Development of a Programme for Long Term Operation of Nuclear Power Plants, vol. 48, IAEA, 2018.
  6. IAEA Services Series No. 19, International Atomic Energy Agency, IRS Guidelines, IAEA, Vienna, 2010.
  7. V.A. Gelovany, A.A. Bashlykov, V.B. Brytkov, E.D. Vyazilov, Intelligent decision support systems in emergency situations using information about the state of the natural environment, Editorial URSS 304 (3) (2001).
  8. V.L. Tikhonovsky, B.K. Bylkin, Place and role of information technologies in decommissioning of NPP power units, Izvestiya vuzov. Nuclear energy. No. 4 (2011) 113-120.
  9. M.A. Yastrebenetsky, Y. Rozen, O. Klevtsov, NPP I&C Systems: General Provisions. Cyber Security and Safety of Nuclear Power Plant Instrumentation and Control Systems, 2020, pp. 1-26, https://doi.org/10.4018/978-1-7998-3277-5.ch001, 2020.
  10. V.V. Sklyar, YuA. Bely, S.A. Malokhatko, Assessment of the software quality of the upper level of information and control systems for nuclear power plants, Radio electronic and computer systems, No. 6 (25) (2007) 153-158.
  11. F.J. Sanchez, The Need for Human Resources in Nuclear Power Programmes. Infrastructure and Methodologies for the Justification of Nuclear Power Programmes, 2012, pp. 147-188, https://doi.org/10.1533/9780857093776.1.147.
  12. V.A. Gorbunov, A.I. Ilchenko, S.G. Andrianov, M.N. Mechtaeva, M.A. Volman, Computer technologies in the system of training specialists for the nuclear industry at ISPU, J. Phys. Conf. 1689 (1) (2020), https://doi.org/10.1088/1742-6596/1689/1/012013.
  13. International Atomic Energy Agency, Spent Fuel Management Options for Research Reactors in Latin America, IAEA, Vienna, 2006. IAEA-TECDOC-1508.
  14. J.M. Scaglione, R.A. Lefebvre, K. Banerjee, G. Radulescu, K.R. Robb, A Unified Spent Nuclear Fuel Database and Analysis System, Oak Ridge National Lab.(ORNL), 2015.
  15. D. Kook, J. Choi, J. Kim, Y. Kim, Review of spent fuel integrity evaluation for dry storage, Nucl. Eng. Technol. V. 45 (1) (2013) 115-124. https://doi.org/10.5516/NET.06.2012.016
  16. S. Alyokhina, A. Kostikov, S. Kruhlov, Safety issues of the dry storage of the spent nuclear fuel, Problems of Atomic Science and Technology 108 (2) (2017) 70-74.
  17. S. Alyokhina, Thermal state of ventilated storage container with spent nuclear fuel under normal operation, Int. J. Nucl. Energy Sci. Technol. 13 (4) (2019) 381-398, https://doi.org/10.1504/IJNEST.2019.106056.
  18. S. Alyokhina, A. Kostikov, D. Lunov, O. Dybach, D. Dimitriieva, Definition of mutual thermal influence of containers with spent nuclear fuel at the open storage site, Nuclear and Radiation Safety v4 (2018) 80.
  19. E.C. Foster, S. Godbole, Database systems: a pragmatic approach, Database systems: A pragmatic approach (2016), https://doi.org/10.1007/978-1-4842-1191-5.
  20. P.P. Chen, Thirty years of ER conferences: milestones, achievements, and future directions (2009), https://doi.org/10.1007/978-3-642-04840-1.
  21. S.V. Alyokhina, V.N. Goloshchapov, A.O. Kostikov, Y.M. Matsevity, Thermal state of ventilated concrete cask with spent nuclear fuel in the conditions of exterior airflow leaking, Nuclear Physics and Atomic Energy 10 (2) (2009) 57-63.
  22. S.V. Alyokhina, S.S. Kapuza, A.O. Kostikov, Solar radiation influence onto the spent nuclear fuel dry storage container, Problems of Atomic Science and Technology 114 (2) (2018) 57-62.
  23. S. Alyokhina, O. S., Dybach, A. Kostikov, D. Dimitrieva, Prediction of the maximum temperature inside container with spent nuclear fuel, Nuclear and Radiation Safety 2 (78) (2018) 31-35, https://doi.org/10.32918/nrs.2018.2(78).05, 2018.
  24. V.G. Rudychev, N.A. Azarenkov, I.O. Girka, Y.V. Rudychev, Change in radiation characteristics outside the SNF storage container as an indicator of fuel rod cladding destruction, Nucl. Eng. Technol. (2021), https://doi.org/10.1016/j.net.2021.05.029.
  25. V.G. Rudychev, N.A. Azarenkov, I.A. Girka, E.V. Rudychev, Irradiation dose minimization by optimizing the arrangement of radiation sources of different intensity, Atom. Energy 119 (4) (2016) 285-290, https://doi.org/10.1007/s10512-016-0061-7.
  26. G. Machin, R. Simpson, G. Sutton, W. Bond, E. Heaps, M. Hayes, J. Jowsey, Novel thermometry approaches to facilitate safe and effective monitoring of nuclear material containers, Nucl. Eng. Des. 371 (2021), https://doi.org/10.1016/j.nucengdes.2020.110939.
  27. H.C. Kim, S.H. Han, Y.J. Lee, Integrity monitoring method for dry storage casks using artificial neural network, Nucl. Eng. Des. 366 (2020), https://doi.org/10.1016/j.nucengdes.2020.110741.