ASTM WK29794

    New Test Method for Analysis of Spent Nuclear Fuel to Determine Selected Isotopes and Estimate Fuel Burnup

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    Developed by Subcommittee: C26.05 | Committee C26 | Contact Staff Manager


    1. Scope

    1. Scope 1.1 A sample of spent nuclear fuel is analyzed to determine uranium and plutonium isotopes, neodymium isotopes, and selected gamma-emitting nuclides (137Cs, 134Cs, 154Eu, 106Ru, and 241Am). Fuel burnup is calculated from the 148Nd-to-fuel ratio as described in this method, which uses an effective 148Nd fission yield calculated from the fission yields of 148Nd for each of the fissioning isotopes weighted according to their contribution to fission as obtained from this method. The burnup value determined in this way require that values be assumed for certain reactor-dependent properties called for in calculations laid out in ASTM E 244. 1.2 Uncertainty associated with the calculated burnup values is discussed in the context of contributions from random and potential systematic error sources associated with the measurements and from uncertainty in the assumed reactor-dependent variables for ASTM E 244. Uncertainties from the needed assumptions are shown to be larger than uncertainties from the isotopic measurements, with the largest effect arising from the value of the fast fission factor. Using the value for this factor that provides the most consistent burnup value between calculated from changes in heavy element isotopic composition (ASTM E 244) and 148Nd Method (ASTM E-321) Standard is needed to measure fuel performance and reprocessing issues in the nuclear fuel cycle


    atom percent fission; mass spectrometric method; nuclear fuel; uranium and plutonium; uranium and plutonium fuel

    The title and scope are in draft form and are under development within this ASTM Committee.

    Citing ASTM Standards
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    Work Item Status

    Date Initiated:

    Technical Contact:
    Delbert Bowers


    C26 (15-01)

    Ballot Item Approved as C1769-2015 and Pending Publication