Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

Neutron dose rate analysis of the new CONSTOR® storage cask for the RBMK-1500 spent nuclear fuel

  • Received : 2020.04.20
  • Accepted : 2020.11.23
  • Published : 2021.06.25
Download PDF
⟨ Previous Next ⟩

Abstract

This paper presents the neutron dose rate analysis of the new CONSTOR® RBMK-1500/M2 storage cask intended for the spent nuclear fuel storage at Ignalina Nuclear Power Plant in Lithuania. These casks are designed to be stored in a new "closed" type interim storage facility, with the capacity to store up to 202 CONSTOR® RBMK-1500/M2 casks. In 2016 y, the "hot trials" of this new facility were conducted and 10 CONSTOR® RBMK-1500/M2 casks loaded with the spent nuclear fuel were transported to the dedicated storage places in this facility. During "hot trials", the dose rate measurements of the CONSTOR® RBMK-1500/M2 casks were performed as the dose rate is one of the critical parameter to control and it must be below design (and safety) criteria. Therefore, having the actual data of the spent nuclear fuel characteristics, the neutron dose rate modeling of the CONSTOR® RBMK-1500/M2 cask loaded with this particular fuel was also performed. Neutron dose rate modeling was performed using MCNP 5 computer code with very detailed geometrical representation of the cask and the fuel. The obtained modeling results were compared with the measurement results and it was revealed, that modeling results are generally in good agreement with the measurements.

Keywords

References

  1. GNS - NUKEM, Lithuanian Energy Institute, Interim Storage of RBMK Spent Nuclear Fuel from Ignalina NPP Units 1 and 2, Environmental Impact Assessment Report S/14658.5.9/EIA-R-04, 2007.
  2. RadEye™ NL personal highly sensitive neutron radiation detectors. https://www.thermofisher.com/order/catalog/product/4250678.
  3. Oak Ridge National Laboratory, SCALE: a Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design, ORNL/TM-2005/39, 2011, Version 6.1.
  4. X-5 Monte Carlo Team, MCNP - a General Monte Carlo N-Particle Transport Code, vols. I-III, 2003 (LA-UR-03-1987, LA-CP-03-0245, LA-CP-03-0284), Version 5.
  5. A. Smaizys, P. Poskas, E. Narkunas, G. Bartkus, Numerical modelling of radionuclide inventory for RBMK irradiated nuclear fuel, Nucl. Eng. Des. 277 (2014) 28-35. https://doi.org/10.1016/j.nucengdes.2014.06.014
  6. E. Narkunas, P. Poskas, A. Smaizys, S. Norris, Estimation of the inventory of 14C and other key radionuclides in irradiated RBMK-1500 graphite based on limited measurements and full 3D core modeling, Radiocarbon 60 (No. 6) (2018) 1849-1859. https://doi.org/10.1017/rdc.2018.122
  7. E. Narkunas, A. Smaizys, P. Poskas, V. Ragaisis, Modelling of RBMK-1500 SNF storage casks activation during very long term storage, Appl. Radiat. Isot. 115 (2016) 100-108. https://doi.org/10.1016/j.apradiso.2016.06.015
  8. J.H. Ko, J.H. Park, I.S. Jung, G.U. Lee, C.Y. Baeg, T.M. Kim, Shielding analysis of dual purpose casks for spent nuclear fuel under normal storage conditions, Nuclear Engineering and Technology 46 (4) (2014) 547-556. https://doi.org/10.5516/net.08.2013.039
  9. P.C. Lai, Y.S. Huang, R.J. Sheu, Comparing the performance of two hybrid deterministic/Monte Carlo transport codes in shielding calculations of a spent fuel storage cask, Nuclear Engineering and Technology 51 (8) (2019) 2018-2025. https://doi.org/10.1016/j.net.2019.06.019
  10. A. Donzella, G. Bonomi, E. Giroletti, A. Zenoni, Biological shielding assessment and dose rate calculation for a neutron inspection portal, Radiat. Phys. Chem. 81 (4) (2012) 414-420. https://doi.org/10.1016/j.radphyschem.2011.12.038
  11. ICRP, Conversion coefficients for use in radiological protection against external radiation, ICRP Publication 74. Ann. ICRP 26 (3-4) (1996).
  12. A. Smaizys, P. Poskas, Radiation safety analysis of the CONSTOR RBMK-1500 cask loaded with spent nuclear fuel, Power Eng. 4 (2000) 73-79 (in Lithuanian).
  13. A. Smaizys, P. Poskas, D. Lukauskas, V. Remeikis, Experimental determination of radiation safety of spent nuclear fuel dry storage casks CASTOR and CONSTOR, Lith. J. Phys. 41 (4-6) (2001) 547-550.
  14. A. Plukis, R. Plukiene, V. Remeikis, R. Davidonis, P. Kucinskas, D. Ridikas, Evaluation of radiation shielding of RBMK-1500 reactor spent nuclear fuel containers, Lith. J. Phys. 46 (3) (2006) 367-374. https://doi.org/10.3952/lithjphys.46309
  15. P. Poskas, A. Smaizys, V. Simonis, Radiological and thermal characteristics of CASTOR RBMK-1500 and CONSTOR RBMK-1500 casks for spent nuclear fuel storage at Ignalina Nuclear Power Plant, Kerntechnik 71 (4) (2006) 222-227. https://doi.org/10.3139/124.100297

Cited by

  1. Comparison of Gamma and Neutron Dose Rate Variations with Time for Cast Iron and Metal-Concrete Casks Used for RBMK-1500 Spent Fuel Storage vol.11, pp.16, 2021, https://doi.org/10.3390/app11167362
  2. Review of modeling experience during operation and decommissioning of RBMK-1500 reactors. II. Radioactive waste management vol.380, 2021, https://doi.org/10.1016/j.nucengdes.2021.111242