Advanced small LWRs, are considered as one of the key design options for the development of a safer nuclear technology considering their inherent safety due to the adoption of passive mitigation strategies and lower nominal power. In the framework of deterministic safety analyses for Small Modular Reactors (SMRs), a model of a generic IRIS SMR was developed by using the severe accident code ASTEC (Study carried out with ASTEC V2, IRSN all rights reserved, [2019]). The ASTEC code thermal-hydraulics modules have been used for the reactor modelling, and the nodalization approach has been described in the present work. The objective of the paper is to analyze the code capability and the consequent applicability to model an integral-type reactor and to simulate the complex thermal–hydraulic phenomena occurring in a passive mitigation strategy. The analysis is based on 2-inches guillotine Direct Vessel Injection (DVI) line break transients.
ASTEC code DBA analysis of a passive mitigation strategy on a generic IRIS SMR / Maccari P.; Mascari F.; Ederli S.; Meloni P.; Manservisi S.. - In: ANNALS OF NUCLEAR ENERGY. - ISSN 0306-4549. - STAMPA. - 156:(2021), pp. 108194.1-108194.17. [10.1016/j.anucene.2021.108194]
ASTEC code DBA analysis of a passive mitigation strategy on a generic IRIS SMR
Manservisi S.
2021
Abstract
Advanced small LWRs, are considered as one of the key design options for the development of a safer nuclear technology considering their inherent safety due to the adoption of passive mitigation strategies and lower nominal power. In the framework of deterministic safety analyses for Small Modular Reactors (SMRs), a model of a generic IRIS SMR was developed by using the severe accident code ASTEC (Study carried out with ASTEC V2, IRSN all rights reserved, [2019]). The ASTEC code thermal-hydraulics modules have been used for the reactor modelling, and the nodalization approach has been described in the present work. The objective of the paper is to analyze the code capability and the consequent applicability to model an integral-type reactor and to simulate the complex thermal–hydraulic phenomena occurring in a passive mitigation strategy. The analysis is based on 2-inches guillotine Direct Vessel Injection (DVI) line break transients.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
