Numerical modelling of radionuclide inventory for RBMK irradiated nuclear fuel

Smaizys, Arturas; Poškas, Povilas; Narkunas, Ernestas; Bartkus, Gytis

doi:10.1016/j.nucengdes.2014.06.014

Cited by 15 publications

(14 citation statements)

References 5 publications

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“…In order to validate the modelling results, available RBMK-1000 reactor fuel experimental data [5,6] and independent TRITON point-depletion calculations results [4] were used to assure that the concentrations predicted by generated cross-section libraries are in a satisfactory agreement. More detailed TRITON calculations are available only for 238 Pu and 240 Pu.…”

Section: Resultsmentioning

confidence: 99%

“…Analyzing other studies performed in this field [7] it was found that possible concentrations of 241 Am in other reactor types show similar results, therefore it is possible that the experimental values are either incorrect or are not presented correctly. Assuming Pu concentrations for different enrichment RBMK-1500 fuel calculated using generated neutron cross-section libraries in constant flux and constant power cases and experimental points from [6] as well as point depletion modelling results from [4]. Pu concentrations for different enrichment RBMK-1500 fuel calculated using generated neutron cross-section libraries in constant flux and constant power cases and experimental points from [6].…”

Section: Americium and Neptuniummentioning

confidence: 99%

“…The SNF composition determination using direct or indirect experimental techniques is rather expensive and technically complicated. Therefore, computer modelling is often used to evaluate SNF characteristics [2][3][4]. However, validation of these results is also essential: results of calculations of various complexity should correspond to available experimental knowledge [5][6][7].…”

Section: Introductionmentioning

confidence: 99%

“…Most of RBMK-1000 reactor physical characteristics are very similar to those of RBMK-1500, therefore the use of experimental data from RBMK-1000 could be justified. Also, some modelling was performed earlier in this area: MCNP and ORIGEN codes were used for the depletion calculations of RBMK-1000 fuel (including comparison with experimental data) in [2,4,13]. The SCALE code system and the HELIOS code were used to calculate concentrations of some nuclides in [14].…”

Section: Introductionmentioning

confidence: 99%

“…Pu concentrations for different enrichment RBMK-1500 fuel calculated using generated neutron cross-section libraries in constant flux and constant power cases and experimental points from [6] as well as point depletion modelling results from [4]. Pu concentrations for different enrichment RBMK-1500 fuel calculated using generated neutron cross-section libraries in constant flux and constant power cases and experimental points from [6].…”

mentioning

confidence: 99%

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generation of RBMK-1500 spent nuclear fuel one-group cross-section libraries and their evaluation against experimental data

et al. 2017

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Depletion of RBMK-1500 spent nuclear fuel (SNF) with and without an erbium burnable absorber was modelled, and onegroup burn-up dependent cross-section libraries for Origen-ARP were created. Depletion calculations for the generation of crosssection libraries were performed using the SCALE 6.1 code package with the TRITON control module, which employs the NEWT deterministic 2D transport code with the 238-group energy library based on the ENDF-B VII library and the ORIGEN-S nuclide composition calculation code. Concentrations of the most important actinides for criticality safety were calculated using the created libraries and were compared with the available experimental data and the newest modelling results. Available experimental data of fission products (Nd and Cs isotopes) were also compared to the modelling results. Composition differences were evaluated for several fuel enrichments and water densities. The comparison shows an acceptable agreement between the values obtained using new one-group cross-section libraries and experimental data except for 238 Pu and 241 Am, as well as the causes of discrepancy are discussed. It has been found that the enrichment and presence of the burnable absorber play an important role in the SNF composition. At the highest evaluated burn-up (29 GWd/tU) isotopic composition differences between 2% enrichment fuel and 2.8% burn-up for actinides important to burn-up credit (BUC) applications varied from 11 to 52%.

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Section: Resultsmentioning

confidence: 99%