2022
DOI: 10.1051/epjn/2022018
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Evaluation of the irradiation-averaged fission yield for burnup determination in spent fuel assays

Abstract: In order to derive the burnup of spent nuclear fuel from the concentration of selected fission products (typically the Nd isotopes and 137Cs), their irradiation-averaged fission yields need to be known with sufficient accuracy, as they evolve with the changes in the actinide vector over the irradiation history. To obtain irradiation-averaged values, radiochemists often resort to robust generic methods – i.e., based on simple mathematical relations – that weight the fission yields according to the actinides con… Show more

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Cited by 4 publications
(15 citation statements)
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“…Indeed, the spike weight does not play a role in eqn (6). 59 It should be noticed that spikes usually contain isotopic impurities (for instance, a 236 U spike usually contains traces of 234 U, 235 U and 238 U isotopes). In many cases, especially for the less abundant isotopes at ultra-trace levels, eqn ( 5) and ( 6) must be modied to include and correct for the contribution of these isotopic impurities.…”
Section: Formula Used For Environmental Samplesmentioning
confidence: 99%
See 2 more Smart Citations
“…Indeed, the spike weight does not play a role in eqn (6). 59 It should be noticed that spikes usually contain isotopic impurities (for instance, a 236 U spike usually contains traces of 234 U, 235 U and 238 U isotopes). In many cases, especially for the less abundant isotopes at ultra-trace levels, eqn ( 5) and ( 6) must be modied to include and correct for the contribution of these isotopic impurities.…”
Section: Formula Used For Environmental Samplesmentioning
confidence: 99%
“…To this end, radionuclide concentrations are accurately determined in environmental samples by ID-MS. It is worth mentioning that isotopic compositions (i.e., 234 U/ 238 U and 230 Th/ 232 Th) are also mandatory for disequilibrium studies, however this topic will not be addressed in this section, as it does not fall under the scope of ID-MS.…”
Section: Isotope Dilution Uncertaintymentioning
confidence: 99%
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“…The BU is expressed relative to the initial amount of uranium. The irradiation-averaged fission yields were calculated using the irradiation history as input according to the method described in (Govers et al, 2022). The BU values were derived from the inventory assuming 200 MeV per fission.…”
Section: Description Of Depletion Codes and Usagementioning
confidence: 99%
“…A sample for a burnup analysis was taken from the region between 1819 mm and 1842 mm. The results of the burnup analysis are reported in , Govers et al (2022) and summarised in Table 2. The inventory of 137 Cs, 143+144 Nd, 145+146 Nd, 148 Nd and 150 Nd for this sample was determined by radiochemical analysis.…”
Section: Introductionmentioning
confidence: 99%