Skip to main content
SpringerLink
Log in

Quantitative and isotopic analysis of released and retained krypton and xenon fission gases from irradiated metallic fuels

  • Published:
Journal of Radioanalytical and Nuclear Chemistry Aims and scope Submit manuscript

Abstract

We quantitatively measured the amounts and isotopic distributions of the released and retained fission gases (Kr and Xe) from two irradiated metallic fuels (U–10Zr and U–10Zr–5Ce) at approximately 2.9 at.% burnup, using a gas chromatography and a quadrupole mass spectrometer. The obtained Xe/Kr ratios indicate that the released and retained fission gases from the irradiated metallic fuels came primarily from the fission of 235U, instead of that of heavy isotopes such as 239Pu and 241Pu. The calculated (83Kr + 84Kr)/86Kr and (131Xe + 132Xe)/134Xe ratios suggest that no fuel rods became defective during the irradiation process.

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

Access this article

Log in via an institution

Price excludes VAT (USA)
Tax calculation will be finalised during checkout.

Instant access to the full article PDF.

Institutional subscriptions

Similar content being viewed by others

References

  1. Pahl RG, Porter DL, Lahm CE, Hofman GL (1990) Experimental studies of U–Pu–Zr fast reactor fuel pins in the experimental breeder reactor-ll. Metall Trans A 21:1863–1870

    Article  Google Scholar 

  2. Hofman GL, Walters LC, Bauer TH (1997) Metallic fast reactor fuels. Prog Nucl Energy 31:83–110

    Article  CAS  Google Scholar 

  3. Sofu T (2015) A review of inherent safety characteristics of metal alloy sodium-cooled fast reactor fuel against postulated accidents. Nucl Eng Technol 47:227–239

    Article  CAS  Google Scholar 

  4. Karahan A, Andrews NC (2013) Extended fuel swelling models and ultra high burn-up fuel behavior of U–Pu–Zr metallic fuel using FEAST-METAL. Nucl Eng Des 258:26–34

    Article  CAS  Google Scholar 

  5. Youn Y-S, Lee J, Kim J-Y, Kim JH, Song H (2016) Change of composition in metallic fuel slug of U–Zr Alloy from high-temperature annealing. Bull Korean Chem Soc 37:1492–1495

    Article  CAS  Google Scholar 

  6. Lee CB, Kim DH, Jung YH (2001) Fission gas release and swelling model of metallic fast reactor fuel. J Nucl Mater 288:29–42

    Article  CAS  Google Scholar 

  7. Huang G-Y, Wirth BD (2012) First-principles study of bubble nucleation and growth behaviors in α U–Zr. J Phys 24:415404

    Google Scholar 

  8. Einziger RE, Seidel BR (1980) Irradiation performance of metallic driver fuel in experimental breeder reactor ΙΙ to high burnup. Nucl Technol 50:25–39

    CAS  Google Scholar 

  9. White RJ, Fisher SB, Cook PMA, Stratton R, Walker CT, Palmer ID (2001) Measurement and analysis of fission gas release from BNFL’s SBR MOX fuel. J Nucl Mater 288:43–56

    Article  CAS  Google Scholar 

  10. Manzel R, Walker CT (2002) EPMA and SEM of fuel samples from PWR rods with an average burn-up of around 100 MWd/kgHM. J Nucl Mater 301:170–182

    Article  CAS  Google Scholar 

  11. Park SD, Kwon HM, Kim DS, Ha YK, Song K (2013) Distribution characteristics of fission gas along the axial direction for an irradiated fuel rod of a pressurized water reactor (PWR). J Radioanal Nucl Chem 298:679–689

    Article  CAS  Google Scholar 

  12. Park SD, Min DK, Ha YK, Song K (2010) The measurement of compositions and the isotopic distribution of released fission gas in the fuel rods of pressurized water reactors (PWR) of Korea. J Radioanal Nucl Chem 284:287–295

    Article  CAS  Google Scholar 

  13. Park SD, Kim J-S, Ha Y-K, Song K (2012) A simple and fast procedure for dissolution of an oxide fuel fragment to extract its retained fission gases. Asian J Chem 24:3267–3273

    CAS  Google Scholar 

  14. Cheon J-S, Kim K-H, Oh S-J, Kim J-H, Lee C-T, Lee B-O, Lee C-B (2013) U–Zr SFR fuel irradiation test in HANARO. In: Technical meeting on design, manufacturing and irradiation behaviour of fast reactors fuels, IAEA-TECDOC-CD-1689, International Atomic Energy Agency, Obninsk (Russian Federation) 211–218

  15. Guide to the expression of uncertainty in measurement (1995) ISBN 92-6r-r10188-9, International Organization for Standardization (ISO)

  16. Jonsson T (1998) Isotopic composition of fission gases in LWR fuel. In: Technical committee on fuel chemistry and pellet-clad interaction related to high burnup fuel, IAEA-TECDOC-1179, International Atomic Energy Agency, Nykoeping (Sweden)

  17. Mogensen M (1983) Determination of fission gas yields from isotope ratios. Int J Mass Spectrom Ion Phys. 48:389–392

    Article  CAS  Google Scholar 

  18. Hiernaut JP, Wiss T, Colle JY, Thiele H, Walker CT, Goll W, Konings RJM (2008) Fission product release and microstructure changes during laboratory annealing of a very high burn-up fuel specimen. J Nucl Mater 377:313–324

    Article  CAS  Google Scholar 

  19. Park SD, Park YS, Ha YK, Song K (2011) The measurement of retained fission gas compositions and their isotopic distributions in an irradiated oxide fuel by inert gas fusion-mass spectrometric analysis. J Radioanal Nucl Chem 289:149–160

    Article  CAS  Google Scholar 

  20. Park SD, Yeon J-W, Ha Y-K, Song K (2012) Inert gas fusion of an irradiated oxide fuel to determine its retained fission gas compositions. Asian J Chem 24:3279–3284

    CAS  Google Scholar 

  21. Larsen E, Egsgaard H, Mogensen M (1983) Mass spectrometric measurement of fission gas from nuclear fuel. Int J Mass Spectrom Ion Phys. 48:385–388

    Article  CAS  Google Scholar 

  22. Noirot J, Desgranges L, Marimbeau P (2002) Contribution of the rim to the overall fission gas release: What do isotopic analyses reveal? In: Seminar on fission gas behaviour in water reactor fuels, Nuclear Energy Agency, Cadarache (France) 223–234

Download references

Acknowledgements

This research was supported by the National Research Foundation of Korea (NRF) funded by the Korean government (MSIP) (Grant No. 2017M2A8A5014754).

Author information

Authors and Affiliations

  1. Nuclear Chemistry Research Division, Korea Atomic Energy Research Institute, 111, Deadeok-daero 989beon-gil, Yuseong-gu, Daejeon, 34057, Republic of Korea

    Young-Sang Youn, Soon Dal Park, Jong-Yun Kim & Yeong-Keong Ha

  2. Radiochemistry & Nuclear Nonproliferation, University of Science & Technology, Gajeong-ro 217, Yuseong-gu, Daejeon, 34113, Republic of Korea

    Jong-Yun Kim

  3. Next Generation Fuel Development Division, Korea Atomic Energy Research Institute, 111, Deadeok-daero 989beon-gil, Yuseong-gu, Daejeon, 34057, Republic of Korea

    Jeong-Yong Park

Authors
  1. Young-Sang Youn
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. Soon Dal Park
    View author publications

    You can also search for this author in PubMed Google Scholar

  3. Jong-Yun Kim
    View author publications

    You can also search for this author in PubMed Google Scholar

  4. Jeong-Yong Park
    View author publications

    You can also search for this author in PubMed Google Scholar

  5. Yeong-Keong Ha
    View author publications

    You can also search for this author in PubMed Google Scholar

Corresponding authors

Correspondence to Young-Sang Youn or Yeong-Keong Ha.

Rights and permissions

Reprints and permissions

About this article

Check for updates. Verify currency and authenticity via CrossMark

Cite this article

Youn, YS., Park, S.D., Kim, JY. et al. Quantitative and isotopic analysis of released and retained krypton and xenon fission gases from irradiated metallic fuels. J Radioanal Nucl Chem 312, 517–521 (2017). https://doi.org/10.1007/s10967-017-5254-6

Download citation

  • Received:

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1007/s10967-017-5254-6

Keywords

Search

Navigation