ASTEC-Na code: Thermal-hydraulic model validation and benchmarking with other codes

Autor: V. Matuzas, M. Haselbauer, S. Ederli, Laurent Laborde, Luis E. Herranz, A. Flores y Flores, Sara Perez-Martin, C. Berna, N. Girault, Giacomino Bandini, Werner Pfrang

Publikováno v: Annals of Nuclear Energy
Annals of Nuclear Energy, Elsevier Masson, 2018, 119, pp.427-439. ⟨10.1016/j.anucene.2017.12.016⟩

International audience; This paper describes the work performed within the WP2.1 of the JASMIN project to validate the thermal-hydraulic models of ASTEC-Na code. The experiments used for validation purposes have been BI1, E8 and EFM1, carried out in

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::a14f32c36866b28d9d2248311c800f13
https://doi.org/10.1016/j.anucene.2017.12.016

Process Distribution in the Network Systems

Autor: J. Augutis, E. Ušpuras, R. Krikštolaitis, V. Matuzas

Publikováno v: Nonlinear Analysis, Vol 12, Iss 2 (2007)

Performing risk analysis of systems, evaluating reliability of technological objects, hazard of technological processes, we usually have to systems of network type and distribution of various processes in such systems. A well-known mathematical appar

Externí odkaz: https://doaj.org/article/f12dba1837bc4b9cb27c2f22f3cc3c6e

Development and assessment of ASTEC-Na fuel pin thermo-mechanical models performed in the European JASMIN project

Autor: Laurent Laborde, Michael Buck, Philippe E. Raison, Sara Perez-Martin, Luis E. Herranz, V. Matuzas, N. Mozzani, A. Flores y Flores, L. Cloarec, B. Farges, N. Girault, Werner Pfrang, F. Feria, Anna Smith

Publikováno v: Annals of Nuclear Energy
Annals of Nuclear Energy, Elsevier Masson, 2018, 119, pp.454-473. ⟨10.1016/j.anucene.2017.12.061⟩

International audience; ASTEC-Na is a computer code system which evaluates protected and unprotected accidents in Sodium-cooled Fast Reactors throughout the Initiation Phase. The fuel pin behavior models implemented in ASTEC-Na simulate the essential

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::19207b819594cc09f48b6a6106ad7729
https://hal.archives-ouvertes.fr/hal-02881821

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

Publikováno v: 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⟩

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 d

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::879e2e37f902d20e2f300643e54210cf
https://publikationen.bibliothek.kit.edu/1000083883/14745246

Coupling decomposition and truncation for the analysis of complex fault trees

Autor: V Matuzas, S Contini

Publikováno v: Proceedings of the Institution of Mechanical Engineers, Part O: Journal of Risk and Reliability. 226:249-261

The analysis of large and complex fault trees is a very difficult task. The main limiting factor is an insufficient working memory. Several methods are available in literature to reduce the working memory requirement including modularization, the so-

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::31ec5860b1d4d8ab9932739838a95bdf
https://doi.org/10.1177/1748006x11401495