Uranium enrichment estimation using MGAU and ISOCS™ codes for nuclear material accountability

Uranium concentration and uranium isotopic content are two important and critical parameters for any nuclear fuel fabrication facilities. In the present study emphasis has been given on the usage of high resolution gamma ray spectrometric (HR-GRS) technique with HPGe detector for the determination of uranium and 235U content in uranium process stream samples. The work has been carried out with an aim to give quick analytical feedback to production facility and also to minimize the generation of analytical waste. These are important requirements for any industrial lab with high analytical load attached to production facility. In this paper a simple and a non-destructive testing (NDT) method has been described for quantification of uranium and 235U content in samples received from UO2 fuel production facilities using HR-GRS technique with high purity germanium (HPGe) detector. A 185.7 keV line of 235U has been used for quantification of uranium in process solutions containing 1  g/L to 600 g/L of uranium covering both aqueous and organic process stream solutions. The results have been compared with that of Davies and Gray method. The limitations associated with gamma ray emitted from daughter products of 238U and self-induced or self-excited X-ray fluorescence lines of uranium have also been studied. Multi Group Analysis of Uranium (MGAU) software code has been used for measurement of 235U content in variety of samples. The results obtained are compared with that of results by thermal ionization mass spectrometer (TIMS).

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Uranium enrichment estimation using MGAU and ISOCS™ codes for nuclear material accountability

Cited by 3 publications

References 3 publications

Material attractiveness of unirradiated depleted, natural and low-enriched uranium for use in radiological dispersal device

Material attractiveness of unirradiated depleted, natural and low-enriched uranium for use in radiological dispersal device

Improving the analysis performance of gamma spectrometer using the Monte Carlo code for accurate measurements of uranium samples

HR GRS-HPGe as NDT method for quantification of uranium and ²³⁵U content in process stream samples from UO₂ fuel production facilities

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Uranium enrichment estimation using MGAU and ISOCS™ codes for nuclear material accountability

Cited by 3 publications

References 3 publications

Material attractiveness of unirradiated depleted, natural and low-enriched uranium for use in radiological dispersal device

Material attractiveness of unirradiated depleted, natural and low-enriched uranium for use in radiological dispersal device

Improving the analysis performance of gamma spectrometer using the Monte Carlo code for accurate measurements of uranium samples

HR GRS-HPGe as NDT method for quantification of uranium and 235U content in process stream samples from UO2 fuel production facilities

Contact Info

Product

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HR GRS-HPGe as NDT method for quantification of uranium and ²³⁵U content in process stream samples from UO₂ fuel production facilities