Nuclear Spent Fuel Parameter Determination using Multivariate Analysis of Fission Product Gamma Spectra

In this paper, we investigate the application of multivariate data analysis methods to the analysis of gamma spectroscopy measurements of spent nuclear fuel (SNF). Using a simulated irradiation and cooling of nuclear fuel over a wide range of cooling times (CT), total burnup at discharge (BU) and initial enrichments (IE) we investigate the possibilities of using a multivariate data analysis of the gamma ray emission signatures from the fuel to determine these fuel parameters. This is accomplished by training a multivariate analysis method on simulated data and then applying the method to simulated, but perturbed, data.We find that for SNF with CT less than about 20 years, a single gamma spectrum from a high resolution gamma spectrometer, such as a high-purity germanium spectrometer, allows for the determination of the above mentioned fuel parameters.Further, using measured gamma spectra from real SNF from Swedish pressurized light water reactors we were able to confirm the operator declared fuel parameters. In this case, a multivariate analysis trained on simulated data and applied to real data was used.

Grape, Sophie,1982-Uppsala universitet,Tillämpad kärnfysik(Swepub:uu)soohl254 (författare)
Jansson, Peter,1971-Uppsala universitet,Tillämpad kärnfysik(Swepub:uu)petejans (författare)
Jacobsson, Staffan,1970-Uppsala universitet,Tillämpad kärnfysik(Swepub:uu)staffjac (författare)
Åberg Lindell, MatildaUppsala universitet,Tillämpad kärnfysik(Swepub:uu)matab118 (författare)
Andersson, Peter,1981-Uppsala universitet,Tillämpad kärnfysik(Swepub:uu)petan574 (författare)
Uppsala universitetTillämpad kärnfysik (creator_code:org_t)

Av författaren/redakt...: Hellesen, Carl, ...; Grape, Sophie, 1 ...; Jansson, Peter, ...; Jacobsson, Staff ...; Åberg Lindell, M ...; Andersson, Peter ...

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