Fission yield measurements by inductively coupled plasma mass-spectrometry

  • Irina Glagolenko
  • Bruce Hilton
  • Jeffrey Giglio
  • Daniel Cummings
Article

Abstract

Correct prediction of the fission products inventory in irradiated nuclear fuels is essential for accurate estimation of fuel burnup, establishing proper requirements for spent fuel transportation and storage, materials accountability and nuclear forensics. Such prediction is impossible without accurate knowledge of neutron induced fission yields. The uncertainty of the fission yields reported in the ENDF/B-VII.0 library is not uniform across all of the data and much of the improvement is desired for certain fissioning isotopes and fission products. We discuss our measurements of cumulative fission yields in nuclear fuels irradiated in thermal and fast reactor spectra using Inductively Coupled Plasma Mass Spectrometry.

Keywords

Cumulative neutron induced fission yields Fission products ICP-MS Mass-spectrometry 

References

  1. 1.
    Chadwick MB, Oblozinsky P, Herman M et al (2006) ENDF/B-VII.0: next generation evaluated nuclear data library for nuclear science and technology. Nucl Data Sheets 107:2931–3060CrossRefGoogle Scholar
  2. 2.
    England TR, Rider BF (1994) Evaluation and compilation of fission yields, ENDF-349, LA-UR-94-3106Google Scholar
  3. 3.
    Lisman FL, Abernathey RM et al (1970) Nucl Sci Eng 42:191–214Google Scholar
  4. 4.
    Maeck WJ, Emel WA et al (1978) Absolute thermal fission yields for 235U, Allied Chemical Corp.-Idaho Chemical Programs Rept., ICP-1142Google Scholar
  5. 5.
    Wolf SF, Bowers DL et al (2005) J Radioanal Nucl Chem 263(3):581–586CrossRefGoogle Scholar
  6. 6.
    Zwicky H-U, Low J et al (2004) Isotopic analysis of irradiated fuels samples in the studsvik hotcell laboratory, Proceedings of the 2004 international meeting on LWR fuel performance, Orlando, Florida, paper 1104, 19–22 September 2004Google Scholar
  7. 7.
    Sullivan VS, Bowers DL (2008) J Radioanal Nucl Chem 277(1):59–64CrossRefGoogle Scholar
  8. 8.
    Clark CR, Moore GA et al (2007) Update on US high density fuel fabrication development, INL/CON-07-12355Google Scholar
  9. 9.
    Chang GS, Ryskamp JM (2000) Depletion analysis of mixed oxide fuel pins in light water reactors and the advanced test reactor. Nucl Technol 129(3):326–337Google Scholar
  10. 10.
    X-5 Monte Carlo Team, MCNP-A general Monte Carlo N-particle transport code, version 5, vol 1, LA-UR-03-1987Google Scholar
  11. 11.
    Croff AG (1983) ORIGEN-2: a versatile computer code for calculating the nuclide compositions and characteristics of nuclear materials. Nucl Technol 62:335–352Google Scholar
  12. 12.
    Toppel BJ (1983) The fuel cycle analysis capability REBUS-3, ANL-83-2, March 1983Google Scholar
  13. 13.
    Yang WS, Finck PJ et al (1992) Reconstruction of pin power and burnup characteristics from nodal calculations in hexagonal geometry. Nucl Sci Eng 111:21Google Scholar
  14. 14.
    McKnight RD (1992) Validation of the REBUS-3/RCT methodologies for EBR-II core-follow analysis, Proceedings of topical meeting on advances in reactor physics. Charleston, SC, March 8–11, 1992, pp 69–80Google Scholar
  15. 15.
    Bell MJ (1973) ORIGEN-The ORNL isotope generation and depletion code, ORNL-4628Google Scholar
  16. 16.
    Compilation and evaluation of fission yield nuclear data, 1991–1996, (2000) IAEA-TECDOC-1168, IAEAGoogle Scholar
  17. 17.
    Mills RW (1995) Fission product yield evaluation. A Thesis, School of Physics and Space Research, University of BirminghamGoogle Scholar
  18. 18.
    Davies W (1970) Absolute measurement of fission yields for 235-uranium and 239-plutonium in the Dounreay fast reactor, LA-4430-MSGoogle Scholar
  19. 19.
    Evans RD (1985) The atomic nucleus. Krieger Publishing Company, Florida, p 144Google Scholar
  20. 20.
    Sommers J, Cummings D et al Advancements in automated gas pressurized extraction chromatography (GPEC) separations. Presentation (Log 109) at the 8th International Conference on Methods and Applications of the Radioanalytical Chemistry, MARC VIII, Kailua-Kona, Hawaii, USA, April 5–10, 2009Google Scholar

Copyright information

© Akadémiai Kiadó, Budapest, Hungary 2009

Authors and Affiliations

  • Irina Glagolenko
    • 1
  • Bruce Hilton
    • 1
  • Jeffrey Giglio
    • 1
  • Daniel Cummings
    • 1
  1. 1.Idaho National LaboratoryIdaho FallsUSA

Personalised recommendations