Toward an improved methodology to simulate the initiating phase of a severe accident in a sodium fast reactor - 15565
Creators
- 1. CEA, Centre de Cadarache, DEN/DTN/SMTA/LPMA, Bat 219, 13108 Saint-Paul-lez-Durance (France)
Description
To consolidate the safety assessment for Sodium Fast Reactors, hypothetical core disruptive accident sequences have been extensively studied over the past decades. These sequences are initiated by a very low probability coincidence of an accident precursor, such as the stop of primary and/or secondary pumps, and failure of one or more safety systems. Regarding Sodium Fast Reactor systems, a major concern is that the core, at nominal, is not necessarily in its most reactive condition concerning neutron transport. From the computational point of view, a severe accident scenario is generally broken down into sub-phases as the initiating phase, the transition phase, the expansion phase and the decay heat-removal phase for applying specific code to each phase. The present research project is dedicated to the analysis and the quantification of bias corresponding to the computational methodology employed to simulate the initiating phase of severe accidents on Sodium Fast Reactors. To evaluate these biases, an extension of existing modeling capabilities is required. To fulfill these needs, a new computational model has been developed. This new model is based on a multi-physics approach through the coupling of the SNATCH kinetics model with the SIMMER-III safety analysis computer code and makes use of modern parallel computing architectures. The computational model has been applied to obtain new information in regards to neutron transport and thermal-hydraulic models and their coupling. (authors)
Availability note (English)
Available (USB stick) from: SFEN, 103 rue Reaumur, 75002 Paris (France)Additional details
Publishing Information
- Publisher
- Societe Francaise d'Energie Nucleaire - SFEN
- Imprint Place
- Paris (France)
- Imprint Title
- ICAPP 2015 Proceedings
- Imprint Pagination
- 3390 p.
- Journal Page Range
- p. 3308-3317
Conference
- Title
- Nuclear Innovations for a low-carbon future
- Acronym
- ICAPP 2015
- Dates
- 3-6 May 2015
- Place
- Nice (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 49010221
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; FAST REACTORS; REACTOR ACCIDENT SIMULATION; REACTOR CORE DISRUPTION; S CODES; SODIUM COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; COMPUTER CODES; EPITHERMAL REACTORS; LIQUID METAL COOLED REACTORS; REACTOR ACCIDENTS; REACTORS; SEVERE ACCIDENTS; SIMULATION
Optional Information
- Notes
- 17 refs.