Extension of ASTEC-Na capabilities for simulating reactivity effects in Sodium Cooled Fast Reactor
| Autor: | Sara Perez-Martin, L. Ammirabile, A. Ponomarev, D. Lemasson, V. Matuzas, L. Cloarec |
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| Přispěvatelé: | Electricité de France, Partenaires INRAE, Karlsruhe Institute of Technology (KIT), Institut de Radioprotection et de Sûreté Nucléaire (IRSN), European Commission, EC |
| Jazyk: | angličtina |
| Rok vydání: | 2018 |
| Předmět: |
[PHYS]Physics [physics]
Technology Computer science 020209 energy Nuclear engineering 02 engineering and technology Accident analysis 01 natural sciences 010305 fluids & plasmas Sodium-cooled fast reactor Nuclear Energy and Engineering Boiling 0103 physical sciences 0202 electrical engineering electronic engineering information engineering Reactivity (chemistry) Transient (computer programming) Single phase ddc:600 |
| Zdroj: | Annals of nuclear energy, 119, 440–453 Annals of Nuclear Energy Annals of Nuclear Energy, Elsevier Masson, 2018, 119, pp.440-453. ⟨10.1016/j.anucene.2017.12.030⟩ |
| ISSN: | 0306-4549 |
| DOI: | 10.1016/j.anucene.2017.12.030⟩ |
| Popis: | International audience; 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. © 2017 The Authors |
| Databáze: | OpenAIRE |
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