Extension of ASTEC-Na capabilities for simulating reactivity effects in Sodium Cooled Fast Reactor. (September 2018)

• Record Type: Journal Article
• Authors: Matuzas, V.; Ammirabile, L.; Cloarec, L.; Lemasson, D.; Perez-Martin, S.; Ponomarev, A.
• Is Part Of: Annals of nuclear energy. Volume 119(2018)
• Page Start: 440
• Page End: 453
• Publication Date: 2018-09
• Subjects: JASMIN project -- Sodium-cooled Fast Reactors -- Neutronic reactivity feedback -- Unprotected flow coast-down -- Severe accidents; Nuclear energy -- Periodicals; Nuclear engineering -- Periodicals; 621.4805
• DOI: 10.1016/j.anucene.2017.12.030
• Languages: English
• ISSNs: 0306-4549

Abstract

Highlights: ASTEC-Na Point Kinetics and reactivity feedback model is presented. ASTEC-Na benchmarking of a ULOF transient against SAS-SFR code results is shown. It has been verified that ASTEC-Na models are correctly implemented. Differences are associated to material expansion and fuel thermo-mechanical models. Abstract: 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.