Skip to main content

Modelling and Spatial Discretization in Depletion Calculations of the Fast Reactor Cell with HELIOS 1.10

  • Chapter
  • First Online:
Computational Modelling and Advanced Simulations

Part of the book series: Computational Methods in Applied Sciences ((COMPUTMETHODS,volume 24))

  • 1263 Accesses

Abstract

The article presents advanced application of computational code HELIOS 1.10 and several application problems of this computer code caused by mathematical solutions of reactor theory physical methods in the program source. The first part of the article presents the HELIOS engineering application on the transmutation fuel cycle modelling where the VVER-440 and SUPERPHENIX fuel assemblies were modelled and compared. The French fast reactor SUPERPHENIX was chosen for the transmutation purposes because this fast reactor is compatible in principle with the Generation IV strategy and Slovakia uses the Russian nuclear reactor VVER-440. The code HELIOS is used mostly for the preparation of few group cross-sections for the use in 3D full core simulation codes. It is necessary to provide its testing and continual improving. The second part of the article refers to one way of sensitivity analysis connected with spatial discretization of the model cells. It shows a very high influence of the spatial discretization on the final results. The maximum effort was aimed at spatial discretization effect and its influence on infinite multiplication factor (kinf) results. Multiplication factor (kinf) reflects the multiplication ability of the relevant SUPERPHENIX and VVER-440 fuel assemblies situated hypothetically into the infinite lattice with no neutron leakage. All kinds of calculations were performed by a spectral code HELIOS 1.10. This study also exposes the HELIOS modelling and simulating borders.

This is a preview of subscription content, log in via an institution to check access.

Access this chapter

Chapter
USD 29.95
Price excludes VAT (USA)
  • Available as PDF
  • Read on any device
  • Instant download
  • Own it forever
eBook
USD 84.99
Price excludes VAT (USA)
  • Available as EPUB and PDF
  • Read on any device
  • Instant download
  • Own it forever
Softcover Book
USD 109.99
Price excludes VAT (USA)
  • Compact, lightweight edition
  • Dispatched in 3 to 5 business days
  • Free shipping worldwide - see info
Hardcover Book
USD 109.99
Price excludes VAT (USA)
  • Durable hardcover edition
  • Dispatched in 3 to 5 business days
  • Free shipping worldwide - see info

Tax calculation will be finalised at checkout

Purchases are for personal use only

Institutional subscriptions

References

  1. Herman, W.O., Westfall, M.R.: ORIGEN-S: SCALE system module to calculation fuel depletion actinide transmutaion, fission product buildup and decay, and associated radiation source terms. ORNL, ORNL/NUREG/CSD-2/V2/R6, vol. 2, section F7 (1998)

    Google Scholar 

  2. Newton, D.T., Hutton, L.J.: The Next Generation WIMS Lattice Code: WIMS9. PHYSOR, Seoul (2002)

    Google Scholar 

  3. Grundmann, U., et al.: DYN3D Version 3.2. Code for Calculation of Transients in Light Water Reactors with Hexagonal or Quadratic Fuel Elements. Code Manual and Input Data Description for Release, Forschungszentrum, Dresden (2007)

    Google Scholar 

  4. Sidorenko, D.V., et al.: Verification of 3-D generation code package for neutronic calculations of VVERs. Proceedings of the 10th Symposium of AER. KFKI, Budapest (2000)

    Google Scholar 

  5. Chadwick, M.B., Obložinský, P., Herman, M.: ENDF/B-VII.0: Next generation evaluated nuclear data library fo nuclear science and technology. Nucl. Data Sheets 107(12), 2931–3060, ISSN 0090-3752 (2006)

    Article  Google Scholar 

  6. US Department of Energy: Office of Nuclear Energy: Science and Technology Advanced Fuel Cycle Initiative (AFCI) Comparison Report, FY 2005. http://afci.sandia.gov/reading_room/reading_list.htm (2005). Accessed 25 Nov 2009

  7. Giust, F.D., Sobieska, M.M., Stamm’ler, R.J.J.: HELIOS: benchmarking against hexagonal TIC lattices. Proceedings of the 7th Symposium of AER. KFKI, Budapest (1997)

    Google Scholar 

  8. Studsvik Scandpower: HELIOS Methods (2008)

    Google Scholar 

  9. JAVYS: Spent Fuel Management: final Solution: Fuel Reprocessing. http://www.javys.sk/en/index.php?page=manazment-vjp/konecne-riesenie/ prepracovanie-paliva (2009). Accessed 30 Nov 2009

  10. Chrapciak, V., Malatin, P.: Inventory from NPP V-1 Jaslovske Bohunice. Proc. 19th Working AER Group E. 19, 1–4 (2009)

    Google Scholar 

  11. Bailly, H. et al.: The Nuclear Fuel of Pressurized Water Reactors and Fast Reactors. Lavoisier Publishing, Paris (1999)

    Google Scholar 

  12. Zajac, R., Darilek, P., Necas, V.: Transmutation of the WWER-440 spent fuel in fast reactor. Proceedings of the 18th Symposium of AER. KFKI, Budapest (2008)

    Google Scholar 

  13. Merk, B., Koch, R.: The effect of spatial discretization in LWR cell calculations with HELIOS 1.9. Proceedings of the 18th Symposium of AER. KFKI, Budapest (2008)

    Google Scholar 

  14. Darilek, P., Zajac, R., Breza, J., Necas, V.: Comparison of PWR-IMF and FR Fuel Cycles. GLOBAL 2007. Advanced Nuclear Fuel Cycles and Systems, Boise (2007)

    Google Scholar 

  15. Darilek, P., Zajac, R.: Sustainable fuel cycle alternatives for small nuclear economies. Proceedings of the 16th Symposium of AER. KFKI, Budapest (2006)

    Google Scholar 

Download references

Acknowledgements

The thanks for this project realization belong to the engineering and research organization VUJE, Inc. that sponsored this project. One of the authors (V. Necas) expresses acknowledgments to the Slovak Grant Agency for Science for support through the grant No. VEGA 1/0685/09.

Author information

Authors and Affiliations

Authors

Corresponding author

Correspondence to R. Zajac .

Editor information

Editors and Affiliations

Rights and permissions

Reprints and permissions

Copyright information

© 2011 Springer Science+Business Media B.V.

About this chapter

Cite this chapter

Zajac, R., Darilek, P., Necas, V. (2011). Modelling and Spatial Discretization in Depletion Calculations of the Fast Reactor Cell with HELIOS 1.10. In: Murín, J., Kompiš, V., Kutiš, V. (eds) Computational Modelling and Advanced Simulations. Computational Methods in Applied Sciences, vol 24. Springer, Dordrecht. https://doi.org/10.1007/978-94-007-0317-9_13

Download citation

  • DOI: https://doi.org/10.1007/978-94-007-0317-9_13

  • Published:

  • Publisher Name: Springer, Dordrecht

  • Print ISBN: 978-94-007-0316-2

  • Online ISBN: 978-94-007-0317-9

  • eBook Packages: EngineeringEngineering (R0)

Publish with us

Policies and ethics