| Hauptseite > Publications database > Neutronic simulations for the FRM II |
| Journal Article | IMPULSE-2019-00189 |
; ; ; ;
2019
Elsevier Science63491
Amsterdam [u.a.]
Please use a persistent id in citations: doi:10.1016/j.anucene.2019.03.010
Abstract: A new high density fuel element consisting of an alloy of uranium-molybdenum (UMo) is being developedfor the conversion of FRM II’s compact core from highly enriched uranium towards lower enricheduranium. Required slight changes of the core geometry demand both neutronic and thermal-hydraulicalre-calculations. This will be achieved by coupled calculations of the deterministic neutronic TORT-TDcode and the thermal-hydraulic system code ATHLET for transient calculations. The calculations presentedhere are used to validate the code and model system for FRM II and are using the current U3Si2fuel. Starting from the well proven full MCNP6 model of FRM II, a substitutional MCNP6 model was developedand validated. Based on this substitutional vertical stack model, a geometrically equivalent andmaterial preserving Serpent 2 model was created. With the validated Serpent 2 model the multi-groupcross sections needed for TORT-TD can be calculated. In the next step, the vertical stack model was translatedinto an r-U-z geometry for TORT-TD. It is shown, that the developed system consisting of data processingtools and new models leads to matching results between Monte Carlo and deterministic codes.With that system of models and post-processing tools, high precision neutronic calculations can easilybe embedded in transient calculations with possible fuel candidates for FRM II.
Keyword(s): Engineering, Industrial Materials and Processing (1st) ; Materials Science (2nd)
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