Burnup Conversion: Convert MWd/kgU or GWd/tU to %

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SUMMARY

The discussion focuses on the conversion of nuclear fuel burnup from MWd/kgU or GWd/tU to percentage (%), specifically for UO2 fuel. It establishes that the conversion ratio varies between 9.38 to 9.75 GWd/tU per 1% FIMA, with a commonly used average of 9.5 GWd/tU/FIMA. The conversion factor is influenced by the neutron energy spectrum and the fission contributions from U-238 and U-235/Pu isotopes. Relevant literature, such as the Nuclear Hydrogen Production Handbook, provides empirical data supporting these conversion ratios.

PREREQUISITES
  • Understanding of nuclear fuel types, specifically UO2
  • Knowledge of burnup measurement units: MWd/kgU and GWd/tU
  • Familiarity with fission processes and isotopes: U-235, U-238, Pu-239
  • Basic principles of neutron energy spectra in nuclear reactions
NEXT STEPS
  • Research the conversion methods for burnup calculations in nuclear engineering
  • Explore the implications of neutron energy spectra on fission rates
  • Study the role of Pu isotopes in nuclear fuel cycles
  • Review the Nuclear Hydrogen Production Handbook for detailed case studies on burnup
USEFUL FOR

Nuclear engineers, reactor physicists, and researchers involved in nuclear fuel management and optimization will benefit from this discussion.

Johnnyfer
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Is there a conversion method to convert burnup from MWd/kgU or GWd/tU into % ? Always assuming that the fuel is UO2 with ~ 200 Mev per fission.
 
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One should be able to take a mass of fuel, either initial moles or grams of U235+U238 in UO2, and determine the energy on the basis of atomic fraction and mass. One can assume 95% TD of UO2 or about 10410 kg/m3 (10.41 gm/cm3), then remember to convert mass of UO2 to mass of U.

I've seen different conversion ratios with a range of something like 9.38 to 9.75 GWd/tU per 1% fima, and some use a mid-range value of 9.5 GWd/tU/fima. The factor depends on the neutron energy spectrum and the proportions of fast fissions in U-238 and in U-235/Pu-239/u-241. The Pu isotopes come from the conversion of U-238 to Pu-239/-240/-241 via neutron capture and subsequent beta decays. The energy release from Pu isotopes is closer to 205 MeV per atom, while that of U-235 is slightly less than 200 MeV. I believe Studsvik-Scandpower has published some papers on the subject.As one example Nuclear Hydrogen Production Handbook, in section 10.2.1.3 (page 223 in the textbook), the authors describe a test in ATR in which fuel achieved burnups of 11.5–19.6% FIMA (108–184 GWd/tU), which gives a conversion ratio of ~9.39 GWd/tU = 1% FIMA), but that's in ATR with the particular type of fuel.
 
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