Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Analysis of the CREOLE experiment on the reactivity temperature coefficient of the UO2 light water moderated lattices using Monte Carlo transport calculations and ENDF/B-VII.1 nuclear data library

  • El Ouahdani, S. (ERPTM Laboratory, Department of Physics, Polydisciplinary Faculty, Sultan Moulay Slimane University) ;
  • Erradi, L. (FSR, Faculty of Sciences, Mohammed V University) ;
  • Boukhal, H. (ERSN, Faculty of Sciences, Abdelmalek Essaadi University) ;
  • Chakir, E. (LHESIR, Faculty of Sciences, Ibn Tofail University) ;
  • El Bardouni, T. (ERSN, Faculty of Sciences, Abdelmalek Essaadi University) ;
  • Boulaich, Y. (CNESTEN) ;
  • Ahmed, A. (ERSN, Faculty of Sciences, Abdelmalek Essaadi University)
  • Received : 2019.08.31
  • Accepted : 2019.11.18
  • Published : 2020.06.25
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Abstract

The CREOLE experiment performed In the EOLE critical facility located In the Nuclear Center of CADARACHE - CEA have allowed us to get interesting and complete experimental information on the temperature effects in the light water reactor lattices. To analyze these experiments with accuracy an elaborate calculation scheme using the Monte Carlo method implemented in the MCNP6.1 code and the ENDF/B-VII.1 cross section library has been developed. We have used the ENDF/B-VII.1 data provided with the MCNP6.1.1 version in ACE format and the Makxsf utility to handle the data in the specific temperatures not available in the MCNP6.1.1 original library. The main purpose of this analysis is the qualification of the ENDF/B-VII.1 nuclear data for the prediction of the Reactivity Temperature Coefficient while ensuring the ability of the MCNP6.1 system to model such a complex experiment as CREOLE. We have analyzed the case of UO2 lattice with 1166 ppm of boron in ordinary water moderator in specified temperatures. A detailed comparison of the calculated effective multiplication factors with the reference ones [1] in room temperature presented in this work shows a good agreement demonstrating the validation of our 3D calculation model. The discrepancies between calculations and the differential measurements of the Reactivity Temperature Coefficient for the analyzed configuration are relatively small: the maximum discrepancy doesn't exceed 1,1 pcm/℃. In addition to the analysis of direct differential measurements of the reactivity temperature coefficient performed in the poisoned UO2 lattice configuration, we have also analyzed integral measurements in UO2 clean lattice configuration using equivalency of the integral temperature reactivity worth with the driver core fuel reactivity worth and soluble boron reactivity worth. In this case both of the ENDF/B-VII.1 and JENDL.4 libraries were used in our analysis and the obtained results are very similar.

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References

  1. CEA/SPRC, CREOLE PWR Reactivity Temperature Coefficient Experiment, Centre de Cadarache", 2008. Rapport CEA - R - 6215.
  2. L. ERRADI, A. SANTAMARINA, O. Ltaize, The reactivity temperature coefficient analysis in light water moderated $UO_2$ and $UO_2-PuO_2$ lattices, Nucl. Sci. Eng. 144 (2003) 47-74. https://doi.org/10.13182/NSE144-47
  3. Denise B. Pelowitz, Andrew J. Fallgren, Garrett E. McMath, "$MCNP6^{TM}$ USER'S MANUAL", Code Version 6.1.1beta, LA-CP-14-00745, Manuel/Los Alamos National Laboratory, June 2014.
  4. Y. Boulaich, et al., CREOLE experiment study on the reactivity temperature coefficient with sensitivity and uncertainty analysis using the MCNP5 code and different neutron cross section evaluations, Nucl. Eng. Des. 241 (8) (2011) 2927-2932. https://doi.org/10.1016/j.nucengdes.2011.06.009
  5. Forrest B. Brown, "The Makxsf Code with Doppler Broadening", LA-UR-06-7002, Los Alamos National Laboratory, 2006.
  6. R.E. MacFarlane, "The NJOY Nuclear Data Processing System Version 2012". LA-UR-12-27079, vol. 20, Los Alamos National Laboratory, 2012. December.
  7. E. Alhassan, E.H.K. Akaho, B.J.B. Nyarko, N.A. Adoo, V.Y. Agbodemegbe, C.Y. Bansah, R. Della, Analysis of reactivity temperature coefficient for light water moderated HEU-UAl4 and LEU-UO2 lattices of MNSR, J. Appl. Sci. Res. 6 (9) (2010) 1431-1439.
  8. L. ERRADI, A.SANTAMARINA. "Analysis of the CREOLE Experiment on the Reactivity Temperature Coefficient Using the APOLLO2 Code and the JEF2.2 Nuclear Data File". DRN/DER/SPRC/LEPh CEA-Cadarache, 13108 Saint Paul Lez Durance Cedex France.
  9. L. Erradi, Etude des effets de temperature dans les reseaux caracteristiques des reacteurs nucleaires de la filiere a eau ordinaire, These de l'Universite de Paris-Sud, Centre d'Orsay, 1982.
  10. S. EL Ouahdani, et al., Monte Carlo analysis of the temperature effect on the infinite multiplication factor for $UO_2$ and $UO_2-PuO_2$ lattices of KRITZ benchmarks, Int. J. Curr. Res. 5 (12) (December 2 2013) 3579-3585.
  11. S. EL Ouahdani, et al., Monte Carlo analysis of KRITZ-2 critical benchmarks on the reactivity temperature coefficient using ENDF/B-VII.1 and JENDL-4.0 nuclear data libraries, Ann. Nucl. Energy 87 (2016) 107-118. https://doi.org/10.1016/j.anucene.2015.07.010
  12. S. EL Ouahdani, et al., A temperature effect analysis of the KRITZ-1 benchmark based on keff decomposition and using the JENDL-4.0 and ENDF/B-VII.1 libraries, Prog. Nucl. Energy 109 (2018) (30 July 2018) 121-129. https://doi.org/10.1016/j.pnucene.2018.07.012
  13. E. Alhassan, N.A. Adoo, G.K. Appiah, A.N. Adazabra, E.A. Alhassan, S.E. Agbemava, V.Y. Agbodemegbe, R. Della, C.Y. Bansah, Analysis of temperature effect on the infinite multiplication factor for HEU-UAl4 and LEU-UO2 lattices of GHARR-1, Res. J. Appl. Sci. Eng. Technol. 3 (3) (2011) 172-178.