Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

NUCLEAR DATA UNCERTAINTY PROPAGATION FOR A TYPICAL PWR FUEL ASSEMBLY WITH BURNUP

  • Rochman, D. (Nuclear Research and Consultancy Group NRG, Petten) ;
  • Sciolla, C.M. (Nuclear Research and Consultancy Group NRG, Petten)
  • Received : 2013.10.21
  • Published : 2014.06.25
Download PDF
⟨ Previous Next ⟩

Abstract

The effects of nuclear data uncertainties are studied on a typical PWR fuel assembly model in the framework of the OECD Nuclear Energy Agency UAM (Uncertainty Analysis in Modeling) expert working group. The "Fast Total Monte Carlo" method is applied on a model for the Monte Carlo transport and burnup code SERPENT. Uncertainties on $k_{\infty}$, reaction rates, two-group cross sections, inventory and local pin power density during burnup are obtained, due to transport cross sections for the actinides and fission products, fission yields and thermal scattering data.

Keywords

References

  1. T. Blyth, M. Avramova, K. Ivanov, E. Royer, E. Sartori, O. Cabellos, H. Feroukhi, and E. Ivanov, "Benchmark for uncertainty analysis in modeling (UAM) for design, operation and safety analysis of LWRs," Tech. Rep. version 2.0, OECD/NEA, 2013.
  2. A. Koning and D. Rochman, "Towards sustainable nuclear energy: Putting nuclear physics to work," Annals of Nuclear Energy, vol. 35, p. 2024, 2008. https://doi.org/10.1016/j.anucene.2008.06.004
  3. D. Rochman, W. Zwermann, S. van der Marck, A. Koning, H. Sjostrand, P. Helgesson, and B. Krzykacz-Hausmann, "Efficient use of Monte Carlo: uncertainty propagation," accepted for publication in Nucl. Sci. and Eng., 2013.
  4. A. Koning, S. Hilaire, and M. Duijvestijn, "Talys-1.0," in proceedings of the International Conference on Nuclear Data for Science and Technology, (Nice, France), April 23-27 2007. www.talys.eu.
  5. R. McFarlane and D. Miur, "The njoy nuclear data processing system, version 91," Tech. Rep. LA-17740-M, Los Alamos National Laboratory, Los Alamos, NM, USA, 1994.
  6. J. Leppanen, "Psg2 / serpent - a continuous-energy monte carlo reactor physics burnup calculation code," tech. rep., VTT Technical Research Centre of Finland, Finland, 2010. http://montecarlo.vtt.fi.
  7. D. Rochman and A. Koning, "Pb and Bi neutron data libraries with full covariance evaluation and improved integral tests," Nucl. Inst. And Meth., vol. A 589, p. 85, 2008.
  8. D. Rochman, A. Koning, D. da Cruz, P. Archier, and J. Tommasi, "On the evaluation of $^{23}Na$ neutron-induced reactions and validations," Nucl. Inst. And Meth., vol. A 612, p. 374, 2010.
  9. D. Rochman, A. Koning, S. van der Marck, A. Hogenbirk, and D. van Veen, "Nuclear data uncertainty propagation: Total Monte Carlo vs. covariance (invited presentation)," in proceedings of the International Conference on Nuclear Data for Science and Technology, April 26-30, 2010, Jeju, Korea, Journ. of Korean Phys. Soc., vol. 59, p. 1236, 2011.
  10. D. Rochman, A. Koning, and S. van der Marck, "Uncertainties for criticality- safety benchmarks and keff distributions," Annals of Nuclear Energy, vol. 36, p. 810, 2009. https://doi.org/10.1016/j.anucene.2009.01.018
  11. A. Koning and D. Rochman, "Modern nuclear data evaluation: Straight from nuclear physics to applications (plenary presentation)," in proceedings of the International Conference on Nuclear Data for Science and Technology, April 26-30, 2010, Jeju, Korea, Journ. of Korean Phys. Soc., vol. 59, p. 773, 2011.
  12. D. Rochman, A. Koning, and S. van der Marck, "Exact nuclear data uncertainty propagation for fusion neutronics calculations," Fusion Engineering and Design, vol. 85, p. 669, 2010. https://doi.org/10.1016/j.fusengdes.2010.03.034
  13. D. Rochman, A. Koning, and S. van der Marck, "Exact nuclear data uncertainty propagation for fusion design," in proceedings of the International Conference on Nuclear Data for Science and Technology, April 26-30, 2010, Jeju, Korea, Journ. of Korean Phys. Soc., vol. 59, p. 1386, 2011. https://doi.org/10.3938/jkps.59.1386
  14. D. Rochman, A. Koning, D. daCruz, and S. van der Marck, "Nuclear data uncertainty propagation for a sodium fast reactor," in proceedings of the International Conference on Nuclear Data for Science and Technology, April 26-30, 2010, Jeju, Korea, Journ. of Korean Phys. Soc., vol. 59, p. 1191, 2011. https://doi.org/10.3938/jkps.59.1191
  15. D. Rochman, A. Koning, S. van der Marck, A. Hogenbirk, and C. Sciolla, "Nuclear data uncertainty propagation: Monte Carlo vs. perturbation," Annals of Nuclear Energy, vol. 38, p. 942, 2011. https://doi.org/10.1016/j.anucene.2011.01.026
  16. D. Rochman, A. Koning, S. van der Marck, A. Hogenbirk, and D. van Veen, "Nuclear data uncertainty propagation: Total Monte Carlo vs. covariance (invited presentation)," in proceedings of the International Conference on Nuclear Data for Science and Technology, April 26-30, 2010, Jeju, Korea, Journ. of Korean Phys. Soc., vol. 59, p. 1236, 2011. https://doi.org/10.3938/jkps.59.1236
  17. D. Rochman, A. Koning, and D. da Cruz, "Uncertainties for the kalimer sodium fast reactor: void coefficient, $k_{eff}$, ${\beta}_{eff}$, burnup and radiotoxicity," 2011. accepted in Journal of Nuclear Science and Technology.
  18. D. Rochman, A. Koning, and D. DaCruz, "Propagation of $^{235,236,238}U$ and $^{239}Pu$ nuclear data uncertainties for a typical PWR fuel element," Nucl. Technology, vol. 179, p. 323, 2012. https://doi.org/10.13182/NT11-61
  19. G. Zerovnik, A. Trkov, D. Rochman, and R. Capote-Noy, "Influence of resonance parameters correlations on the resonance integral uncertainty; $^{55}Mn$ case," Nucl. Inst. And Meth., vol. A 632, p. 137, 2011.
  20. D. Rochman and A. Koning, "How to randomly evaluate nuclear data: a new method applied to $^{239}Pu$," Nucl. Sci. and Eng., 2011. accepted for publication in Nucl. Sci. and Eng.
  21. D. Rochman and A. Koning, "Evaluation and adjustement of the neutron- induced reactionsof $^{63,65}Cu$," Nucl. Sci. And Eng., vol. 170, p. 265, 2012. https://doi.org/10.13182/NSE11-37
  22. A. Koning and D. Rochman, "TENDL-2008: Consistent talys-based evaluated nuclear data library including covariance data," Tech. Rep. NEA/WPEC JEF- DOC-1262, NEA Nuclear Data Bank, Paris, France, 2008.
  23. A. Koning and D. Rochman, "TENDL-2009: Consistent talys-based evaluated nuclear data library including covariance data," Tech. Rep. NEA/WPEC JEF- DOC-1310, NEA Nuclear Data Bank, Paris, France, 2009.
  24. A. Koning and D. Rochman, "TENDL-2010: Consistent talys-based evaluated nuclear data library including covariance data," Tech. Rep. NEA/WPEC JEF- DOC-1349, NEA Nuclear Data Bank, Paris, France, 2010.
  25. A. Koning and D. Rochman, "TENDL-2010: Consistent talys-based evaluated nuclear data library including covariance data," tech. rep., available at www.talys.eu/tendl-2011, 2011.
  26. R. McFarlane, "Njoy99 - code system for producing pointwise and multigroug neutron and photon cross sections from endf/b data," Tech. Rep. RSIC PSR-480, Los Alamos National Laboratory, Los Alamos, NM, USA, 2000.
  27. D. Rochman and C. Sciolla, "Total Monte Carlo Uncertainty propagation applied to the Phase I-1 burnup calculation (a report for the pin-cell physics of TMI-1 PWR unit cell of the OECD/UAM working group)," tech. rep., NRG, Petten, the Netherlands, 2012. NRG Report 113696.
  28. D. Rochman and A. Koning, "How to randomly evaluate nuclear data: a new method applied to $^{239}Pu$," Nucl. Sci. And Eng., vol. 169, p. 68, 2011. https://doi.org/10.13182/NSE10-66
  29. A. Koning, M. Duijvestijn, S. van der Marck, R. K. Meulekamp, and A. Hogenbirk, "New nuclear data libraries for lead and bismuth and their impact on accelerator-driven systems design," Nucl. Sci. and Eng., vol. 156, p. 357, 2007. https://doi.org/10.13182/NSE156-357
  30. A. Koning and J. Delaroche Nucl. Phys., vol. A 713, p. 231, 2003.
  31. H. Henriksson, O. Schwerer, D. Rochman, M. Mikhaylyukova, and N. Otuka, "The art of collecting experimental data internationally: EXFOR, CINDA and the NRDC network," in proceedings of the International Conference on Nuclear Data for Science and Technology, (Nice, France), p. 197, April 23-27 2007.
  32. M. Chadwick, P. Oblozinsky, M. Herman, N. Greene, R. McKnight, D. Smith, P. Young, R. MacFarlane, G. Hale, S. Frankle, A. Kahler, T. Kawano, R. Little, D. Madland, P. Moller, R. Mosteller, P. Page, P. Talou, H. Trellue, M. White, W. Wilson, R. Arcilla, C. Dunford, S. Mughabghab, B. Pritychenko, D. Rochman, A. Sonzogni, C. Lubitz, T. Trumbull, J. Weinman, D. Brown, D. Cullen, D. Heinrichs, D. McNabb, H. Derrien, M. Dunn, N. Larson, L. Leal, A. Carlson, R. Block, J. Briggs, E. Cheng, H. Huria, M. Zerkle, K. Kozier, A. Courcelle, V. Pronyaev, and S. van der Marck, "ENDF/B-VII.0: Next generation evaluated nuclear data library for nuclear science and technology," Nuclear Data Sheets, vol. 107, p. 2931, 2006. https://doi.org/10.1016/j.nds.2006.11.001
  33. S. Mughabghab, Atlas of Neutron Resonances: Thermal Cross Sections and Resonance Parameters. Amsterdam: Elsevier, 2006.
  34. P. Talou, "Prompt fission neutrons calculations in the madland-nix model," Tech. Rep. LA-UR-07-8168, Los Alamos National Laboratory, Los Alamos, NM, USA, December 2007.
  35. D. Madland and J. Nix Nucl. Sci. and Eng., vol. 81, p. 213, 1982. https://doi.org/10.13182/NSE82-5
  36. A. Wahl, "Systematics of fission-product yields," Tech. Rep. LA-13928, Los Alamos National Laboratory, Los Alamos, NM, USA, May 2002.
  37. D. Rochman and A. Koning, "Improving the H in $H_2O$ thermal scattering data using the Petten method," vol. 172, p. 287, 2012. Nucl. Sci. and Eng. https://doi.org/10.13182/NSE12-2