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A procedure for verification of Studsvik's spent nuclear fuel code SNF

Verfahren zur Verifikation des Codes von Studsvik für abgebrannte Kernbrennstoffe SNF
T. Simeonov and C. Wemple
From the journal Kerntechnik


Studsvik's approach to spent nuclear fuel analyses combines isotopic concentrations and cross-sections, calculated by the lattice physics codes, with core irradiation history data from reactor core simulator and tabulated isotopic decay data. These data sources are used and processed by the code Spent Nuclear Fuel (SNF) to predict spent nuclear fuel characteristics. The procedure for verification and validation of SNF is outlined in this paper which includes verification of the decay data as well as the numerical methods where they are applied into. The paper presents the applicability of SNF to analyses of spent nuclear fuel in comparisons to well established and recognized code in the spent fuel analyses field, ORIGEN, SCALE v6.2.2.


Studsviks Ansatz für die Analyse abgebrannter Kernbrennstoffe kombiniert Isotopenkonzentrationen und -querschnitte, die durch die Gitter-Codes berechnet werden, mit Daten zur Geschichte der Kernbestrahlung aus dem Reaktorkernsimulator und tabellarischen Isotopenzerfallsdaten. Diese Datenquellen werden vom Code SNF verwendet und verarbeitet, um die Eigenschaften abgebrannter Kernbrennstoffe vorherzusagen. Das Verfahren zur Verifikation und Validierung des SNF Codes wird in diesem Beitrag skizziert, der sowohl die Verifikation der Zerfallsdaten als auch die numerischen Methoden, in denen sie angewendet werden, umfasst. Dieser Beitrag stellt die Anwendbarkeit des SNF auf Analysen von abgebrannten Kernbrennstoffen im Vergleich zu gut etablierten und anerkannten Codes im Bereich der Analysen von abgebrannten Brennelementen dar wie ORIGEN, SCALE v6.2.2.



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Received: 2019-01-14
Published Online: 2019-08-27
Published in Print: 2019-09-16

© 2019, Carl Hanser Verlag, München