DOI QR코드

DOI QR Code

Evaluation of nuclear material accountability by the probability of detection for loss of Pu (LOPu) scenarios in pyroprocessing

  • Woo, Seung Min (Department of Nuclear Engineering, Texas A&M University) ;
  • Chirayath, Sunil S. (Department of Nuclear Engineering, Texas A&M University)
  • Received : 2018.04.18
  • Accepted : 2018.08.20
  • Published : 2019.02.25

Abstract

A new methodology to analyze the nuclear material accountability for pyroprocessing system is developed. The $Pu-to-^{244}Cm$ ratio quantification is one of the methods for Pu accountancy in pyroprocessing. However, an uncertainty in the $Pu-to-^{244}Cm$ ratio due to the non-uniform composition in used fuel assemblies can affect the accountancy of Pu. A random variable, LOPu, is developed to analyze the probability of detection for Pu diversion of hypothetical scenarios at a pyroprocessing facility considering the uncertainty in $Pu-to-^{244}Cm$ ratio estimation. The analysis is carried out by the hypothesis testing and the event tree method. The probability of detection for diversion of 8 kg Pu is found to be less than 95% if a large size granule consisting of small size particles gets sampled for measurements. To increase the probability of detection more than 95%, first, a new Material Balance Area (MBA) structure consisting of more number of Key Measurement Points (KMPs) is designed. This multiple KMP-measurement for the MBA shows the probability of detection for 8 kg Pu diversion is greater than 96%. Increasing the granule sample number from one to ten also shows the probability of detection is greater than 95% in the most ranges for granule and powder sizes.

Keywords

References

  1. International Atomic Energy Agency (IAEA), IAEA Safeguards Glossary 2001 Edition, 2001.
  2. Nuclear Material Accounting Handbook, IAEA Services Series No. 15, 2008.
  3. P.C. Durst, R. Wallace, I. Therios, M.H. Ehinger, R. Bean, D.N. Kovacic, A. Dougan, K. Tolk, B. Boyer, Advanced Safeguards Approaches for New Reprocessing Facilities, 2007.
  4. R. Avenhaus, Material Accountability: Theory, Verification, and Applications, John Wiley & Sons, Chichester, UK, 1977.
  5. B. Han, H. Shin, H. Kim, Analysis of measurement uncertainty of material unaccounted for in the reference pyroprocessing facility, Nucl. Technol. 182 (2013).
  6. H.L. Chang, F.X. Gao, W.I. Ko, H.D. Kim, S.Y. Lee, Evaluation of sigma-MUF (Material Unaccounted For) for the conceptually designed Korea advanced pyroprocess facility, J. Kor. Phys. Soc. 59 (2011) 1418, https://doi.org/10.3938/jkps.59.1418.
  7. N. Miura, H.O. Menlove, The Use of Curium Neutrons to Verify Plutonium in Spent Fuel and Reprocessing Wastes, 1994.
  8. T.-H. Lee, Y.-S. Kim, T.-J. Kwon, H.-S. Shin, H.-D. Kim, Determination of the plutonium mass and curium ratio of spent fuel assemblies for input nuclear material accountancy of pyroprocessing, and analysis of their errors, Nucl. Technol. 179 (2012) 196-204. https://doi.org/10.13182/NT11-77
  9. M. Gonzalez, L. Hansen, D. Rappleye, R. Cumberland, M.F. Simpson, Application of a one-dimensional transient electrorefiner model to predict partitioning of plutonium from curium in a pyrochemical spent fuel treatment process, Nucl. Technol. 192 (2015) 165-171, https://doi.org/10.13182/NT15-28.
  10. H. Lee, G. Il Park, J.W. Lee, K.H. Kang, J.M. Hur, J.G. Kim, S. Paek, I.T. Kim, I.J. Cho, Current status of pyroprocessing development at KAERI, Sci. Technol. Nucl. Install 2013 (2013) 1-11.
  11. T.H. Lee, H.O. Menlove, S.Y. Lee, H.D. Kim, Development of the ACP safeguards neutron counter for PWR spent fuel rods, Nucl. Instrum. Methods Phys. Res., Sect. A 589 (2008) 57-65, https://doi.org/10.1016/j.nima.2008.02.054.
  12. T.H. Lee, H.D. Kim, J.S. Yoon, S.Y. Lee, M. Swinhoe, H.O. Menlove, Preliminary calibration of the ACP safeguards neutron counter, Nucl. Instruments methods Phys. Res. Sect. A Accel. Spectrometers, Detect. Assoc. Equip 580 (2007) 1423-1427, https://doi.org/10.1016/j.nima.2007.07.142.
  13. T.H. Lee, Y.S. Kim, H.-S. Shin, H.-D. Kim, Hot-test results of the advanced spent fuel conditioning process safeguards neutron counter for PWR spent fuel rods, Nucl. Technol. 176 (2011) 147-154, https://doi.org/10.13182/NT11-A12549.
  14. T.H. Lee, H.D. Kim, Application of a self-multiplication correction method to a neutron coincidence counter and its calibration for spent fuel, IEEE Trans. Nucl. Sci. 56 (2009) 2791-2795, https://doi.org/10.1109/TNS.2009.2021427.
  15. H. Seo, B.H. Won, S.K. Ahn, S.K. Lee, S.H. Park, G. Il Park, S.H. Menlove, Optimization of hybrid-type instrumentation for Pu accountancy of U/TRU ingot in pyroprocessing, Appl. Radiat. Isot. 108 (2016) 16-23, https://doi.org/10.1016/j.apradiso.2015.11.109.
  16. R.A. Borrelli, Use of curium spontaneous fission neutrons for safeguardability of remotely-handled nuclear facilities: fuel fabrication in pyroprocessing, Nucl. Eng. Des. 260 (2013) 64-77, https://doi.org/10.1016/j.nucengdes.2013.03.025.
  17. R.A. Borrelli, Functional components for a design strategy: hot cell shielding in the high reliability safeguards methodology, Nucl. Eng. Des. 305 (2016) 18-27, https://doi.org/10.1016/j.nucengdes.2016.05.010.
  18. S.M. Woo, S.S. Chirayath, M. Fratoni, Nuclide Composition Non-uniformity in Used Nuclear Fuel for Considerations in Pyroprocessing Safeguards, 2018. Nucl. Eng. Technol. (n.d.), https://doi.org/10.1016/j.net.2018.05.011.
  19. J. Hayya, D. Armstrong, N. Gressis, A note on the ratio of two normally distributed variables, Manag. Sci. 21 (1975) 1338-1341, https://doi.org/10.1287/mnsc.21.11.1338.
  20. H. Yu, Low-Boron OPR1000 Core Based on the BigT Burnable Absorber, KAIST, 2014.
  21. H. Yu, M.S. Yahya, Y. Kim, A reduced-boron OPR1000 core based on the BigT burnable absorber, Nucl. Eng. Technol 48 (2016) 318-329, https://doi.org/10.1016/j.net.2015.12.010.
  22. S.K. Kim, W.I. Ko, S.R. Youn, R. Gao, Cost analysis of a commercial pyroprocess facility on the basis of a conceptual design in Korea, Ann. Nucl. Energy 80 (2015) 28-39. https://doi.org/10.1016/j.anucene.2015.01.011
  23. J.-H. Yoo, C.-S. Seo, E.-H. Kim, H.-S. Lee, A conceptual study of pyroprocessing for recovering actinides from spent oxide fuels, Nucl. Eng. Technol 40 (2008) 581-592, https://doi.org/10.5516/NET.2008.40.7.581.
  24. N.J. McCormick, Reliability and Risk Analysis: Methods and Nuclear Power Applications, Academic Press, New York, 1981.