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Extension of ASTEC-Na capabilities for simulating reactivity effects in Sodium Cooled Fast Reactor

Matuzas, V.; Ammirabile, L.; Cloarec, L.; Lemasson, D.; Perez-Martin, S.; Ponomarev, A.

The EU-JASMIN project (7th FP of EURATOM) has been centred on the development and validation of the new severe accident analysis code ASTEC-Na (Accident Source Term Evaluation Code) for Sodium-cooled Fast Reactors (SFR). The development of such computational tool being able to assist safety analysis of innovative reactor concepts is of crucial importance. One of the challenging issues when modelling SFRs is the neutronic reactivity feedbacks. This paper presents the model implemented in ASTEC-Na for representing the reactivity effects in SFR as well as the benchmarking results of a ULOF transient against SAS-SFR code results. It has been verified that the models are correctly implemented and that ASTEC-Na is now able to calculate reactivity feedbacks not only in the sodium single phase, but also after boiling onset and fuel in-pin relocation.

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Verlagsausgabe §
DOI: 10.5445/IR/1000083883
Veröffentlicht am 25.06.2018
DOI: 10.1016/j.anucene.2017.12.030
Zitationen: 1
Web of Science
Zitationen: 1
Zugehörige Institution(en) am KIT Institut für Neutronenphysik und Reaktortechnik (INR)
Publikationstyp Zeitschriftenaufsatz
Jahr 2018
Sprache Englisch
Identifikator ISSN: 0306-4549
KITopen-ID: 1000083883
HGF-Programm 32.01.12 (POF III, LK 01)
Erschienen in Annals of nuclear energy
Band 119
Seiten 440–453
Nachgewiesen in Web of Science
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