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Application of FLUKA and OpenMC in coupled physics calculation of target and subcritical reactor for ADS

  • Ze-Long Zhao
  • Yong-Wei YangEmail author
  • Shuang Hong
Article
  • 17 Downloads

Abstract

The study of accelerator-driven subcritical reactor systems (ADSs) has been an important research topic in the field of nuclear energy for years. The main code applied in ADS research is MCNPX, which was developed by Los Alamos National Laboratory. We studied the application of the open-source Monte Carlo codes FLUKA and OpenMC to a coupled ADS calculation. The FLUKA code was used to simulate the reaction of high-energy protons with the nucleus of the target material in the ADS, which produces spallation neutrons. Information on the spallation neutrons, such as their energy, position, direction, and weight, can be recorded by a user-defined routine called FLUSCW provided by FLUKA. Then, the information was stored in an external neutron source file in HDF5 format by using a conversion code, as required by the OpenMC calculation. Finally, the fixed-source calculation function of OpenMC was applied to simulate the transport of spallation neutrons and obtain the distribution of the neutron flux in the core region. In the coupled calculation, the high-energy cross-section library JENDL4.0/HE in ACE format produced by NJOY2016 was applied in the OpenMC transport simulation. The OECD–ADS benchmark problem was calculated, and the results were compared with those obtained using MCNPX. It was found that the flux calculations performed by FLUKA–OpenMC and MCNPX were in agreement, so the coupling calculation method for ADS is reasonable and feasible.

Keywords

Accelerator-driven subcritical system MCNPX FLUKA OpenMC JENDL4.0/HE NJOY2016 

References

  1. 1.
    N. Aizawa, F. Kubo, T. Iwasaki, Comparison of different neutronics analysis technique for accelerator-driven system. Ann. Nucl. Energy 60, 368–373 (2013).  https://doi.org/10.1016/j.anucene.2013.05.019 CrossRefGoogle Scholar
  2. 2.
    W.L. Zhan, H.S. Xu, Advanced fission energy program—ADS transmutation system. Bull. Chin. Acad. Sci. 27, 375–383 (2012).  https://doi.org/10.3969/j.issn.1000-3045.2012.03.017. (in Chinese) CrossRefGoogle Scholar
  3. 3.
    D.B. Pelowitz (ed.), MCNPX User’s Manual, Version 2.7.0 (Los Alamos National Laboratory, New Mexico, 2011)Google Scholar
  4. 4.
    A. Krasa, Spallation Reaction Physics (2010), http://ojs.ujf.cas.cz/~krasa/ZNTT/SpallationReactions-text.pdf. Accessed 20 Jul 2017
  5. 5.
    K. Niita, H. Takada, S.I. Meigo et al., High-energy particle transport code NMTC/JAM. Nucl. Instrum. Methods B 184, 406–420 (2001).  https://doi.org/10.1016/S0168-583X(01)00784-4 CrossRefGoogle Scholar
  6. 6.
    A. Ferrari, P.R. Sala, A. Fasso et al., FLUKA: a multi-particle transport code. Lancet 10(7740), 44–45 (2005).  https://doi.org/10.2172/877507 CrossRefGoogle Scholar
  7. 7.
    S. Agostinelli, J. Amako, K. Amako et al., Geant4—a simulation toolkit. Nucl. Instrum. Methods A 506(3), 250–303 (2003).  https://doi.org/10.1016/S0168-9002(03)01368-8 CrossRefGoogle Scholar
  8. 8.
    Y. Kadi, in Advanced Monte Carlo for Radiation Physics, Particle Transport Simulation and Applications, ed. by A. Kling, et al. (Springerg Berlin Heidelberg, New York, 2001), p. 1015CrossRefGoogle Scholar
  9. 9.
    P. Neuhold, Influence of the FLUKA geometrical model on the ADS demonstration facility criticality calculations. Paper presented at Proceedings of the Monte Carlo 2000 Conference, Lisbo, Portugal, 23–26 October, 2000Google Scholar
  10. 10.
    T. Sasa, K. Tsujimoto, T. Takizuka et al., Code development for the design study of the OMEGA Program accelerator-driven transmutation systems. Nucl. Instrum. Methods A 463(3), 495–504 (2001).  https://doi.org/10.1016/S0168-9002(01)00166-8 CrossRefGoogle Scholar
  11. 11.
    S. Zhou, H. Wu, L. Cao et al., LAVENDER: a steady-state core analysis code for design studies of accelerator driven subcritical reactors. Nucl. Eng. Des. 278, 434–444 (2014).  https://doi.org/10.1016/j.nucengdes.2014.07.027 CrossRefGoogle Scholar
  12. 12.
    P.K. Romano, B. Forget, The OpenMC Monte Carlo particle transport code. Ann. Nucl. Energy 51, 274–281 (2013).  https://doi.org/10.1016/j.anucene.2012.06.040 CrossRefGoogle Scholar
  13. 13.
    P.K. Romano, N.E. Horelik, B.R. Herman et al., OpenMC: a state-of-the-art Monte Carlo code for research and development. Ann. Nucl. Energy 82, 90–97 (2014).  https://doi.org/10.1016/j.anucene.2014.07.048 CrossRefGoogle Scholar
  14. 14.
    The HDF Group, HDF5 User’s Guide, Release 1.10 (2015), https://support.hdfgroup.org/HDF5/doc/UG/HDF5__Users_Guide.pdf. Accessed 27 Jul 2017
  15. 15.
    A.C. Kahler (ed.), The NJOY Nuclear Data Processing System, Version 2016 (Los Alamos National Security, New Mexico, 2016)Google Scholar
  16. 16.
    A. Ferrari, P. R. Sala, A. Fasso et al, The FLUKA user routines: how to tailor FLUKA to specific user’s needs. Paper presented at 8th FLUKA Course, National Center of Scientific Research “Demokritos”, Athens, Greece, 30 March - 3 April 2009Google Scholar
  17. 17.
    X.Z. Li, H.C. Wu, Y.Q. Zheng et al., Development and application of high-energy nuclear data library for accelerator driven sub-critical system. Atom. Energy Sci. Technol. 49(Z1), 371–376 (2015).  https://doi.org/10.7538/yzk.2015.49.s0.0371. (in Chinese) CrossRefGoogle Scholar
  18. 18.
    S. Kunieda et al., Overview of JENDL-4.0/HE and benchmark calculation. Paper presented at Proceedings of the 2015 Symposium on Nuclear Data, Ibaraki Quantum Beam Research Center, Tokai-mura, Ibaraki, Japan, 19–20 November 2015Google Scholar
  19. 19.
    R.E. Macfarlane, A.C. Kahler, Methods for processing ENDF/B-VII with NJOY. Nucl. Data Sheets 111(12), 2739–2890 (2017).  https://doi.org/10.1016/j.nds.2010.11.001 CrossRefGoogle Scholar
  20. 20.
    Organisation for Economic Co-operation and Development/Nuclear Energy Agency, Comparison Calculations for an Accelerator Driven Minor Actinide Burner (OECD, Paris, 2002)Google Scholar
  21. 21.
    B.C. Na, M. Cometto, P. Wydler et al., OECD/NEA comparison calculations for an accelerator-driven system using different nuclear data libraries. J. Nucl. Sci. Technol. 39(sup2), 835–840 (2002).  https://doi.org/10.1080/00223131.2002.10875229 CrossRefGoogle Scholar

Copyright information

© China Science Publishing & Media Ltd. (Science Press), Shanghai Institute of Applied Physics, the Chinese Academy of Sciences, Chinese Nuclear Society and Springer Nature Singapore Pte Ltd. 2019

Authors and Affiliations

  1. 1.Institute of Modern PhysicsChinese Academy of SciencesLanzhouChina
  2. 2.School of Nuclear Science and Technology, University of Chinese Academy of SciencesBeijingChina
  3. 3.University of Science and TechnologyHefeiChina

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