Analysis of Calculation Model for Primary Coolant Fission Products

2023;
: pp. 69 – 74
https://doi.org/10.23939/jeecs2023.02.069
Received: August 21, 2023
Revised: October 30, 2023
Accepted: November 21, 2023

S. Lys. Analysis of calculation model for primary coolant fission products. Energy Engineering and Control Systems, 2023, Vol. 9, No. 2, pp. 69 – 74. https://doi.org/10.23939/jeecs2023.02.069

Authors:
1
Lviv Polytechnic National University

The sources of radioactive contamination of the primary coolant by fission products when the unit is operating at the rated power are as follows: defect fuel elements with gas leakiness and substantial damages, surface contamination of the outer surfaces of fuel claddings, superficial contamination of structural materials of fuel assemblies. Initially in the reactor operation (if there are no manufacturing defects in fuel elements), the contamination of the coolant by fission products is determined by the release into the reactor coolant circuit of fission fragments of Uranium-235 (due to their kinetic energy) that is present on the outer surfaces of fuel elements as contamination in their manufacturing. During normal operation of the reactor, the integrity of cladding may fail due to various processes of corrosion fatigue type. These processes result in, first of all, micro-fissures and then in large defects in the claddings, which is accompanied by an increase in the release of fission products from fuel elements into the primary coolant.

  1. FINAL Safety Analysis Report. (2010) Radioactive waste Management. R01.KK.0.0.OO.FSAR.WD0R0.
  2. Preliminary safety analysis reports. (1997) “General Provisions for Ensuring Safety of Nuclear Power Plants” NP-001-97 (PNAEG-01-011-97, OPB-88/97).
  3. Semerak, M., Lys, S., & Kovalenko, T. (2019) Analysis of the process of plasma processing of radioactive waste. Nuclear and radiation safety, 1(81), 23-29. https://doi.org/10.32918/nrs.2019.1(81).04
  4. Nosovskyy A. V., Aleksyeyeva Z. M., Borozenets H. P. et al. (2007) Radioactive Waste Management, Ed. Nosovskyy A. V., Tekhnika, Kyiv, 368 p. (in Ukrainian)
  5. 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, N.5(135). 88–97. https://doi.org/10.46813/2021-135-088
  6. Gavrilovskiy D. V. et al. (2016) On the disposal of radioactive waste from nuclear reactors in Russia. Proceeding of Higher Educational Institutions. North-Caucasus region. Natural science. No. 4, 62–66. (in Russian)
  7. Saeed Ehsan Awan, Sikander M. Mirza, Nasir M. Mirza (2011) Sensitivity analysis of fission product activity in primary coolant of typical PWRs. Progress in Nuclear Energy, Volume 53, Issue 3. 245-249. https://doi.org/10.1016/j.pnucene.2010.11.002
  8. M. Javed Iqbal, Nasir M. Mirza, Sikander M. Mirza. (2007) Kinetic simulation of fission product activity in primary coolant of typical PWRs under power perturbations. Nuclear Engineering and Design, Volume 237, Issue 2. 199-205. https://doi.org/10.1016/j.nucengdes.2006.06.003
  9. M. Asadollahzadeh Goudarzi, Kh. Rezaee Ebrahim Saraee, A.R. Tabesh, B. Teymuri, H. Mansouri (2015) Calculation of the activity of fission products in the primary coolant of the eastern-type pressurized water reactor (VVER1000-V446) of the Bushehr Nuclear Power Plant at normal full power operational condition. Progress in Nuclear Energy, Volume 81, 123-126. https://doi.org/10.1016/j.pnucene.2014.09.019
  10. Hakim Mazrou. (2009) Performance improvement of artificial neural networks designed for safety key parameters prediction in nuclear research reactors. Nuclear Engineering and Design, Volume 239, Issue 10, 1901-1910. https://doi.org/10.1016/j.nucengdes.2009.06.004