Preliminary accident analysis of Flexblue underwater reactor - 15149
Creators
- 1. DCNS, 143 bis Avenue de Verdun, 92442 Issy-les-Moulineaux (France)
Description
Flexblue is a sub-sea-based, transportable, small modular reactor delivering 160 MWe. Immersion provides the reactor with an infinite heat sink - the ocean - around the metallic hull. The reference design includes a loop-type PWR with 2 horizontal steam generators. The safety systems are designed to operate passively: safety functions are fulfilled without operator action and external electrical input. Residual heat is removed through 4 natural circulation loops: two primary heat exchangers immersed in safety tanks cooled by seawater and two emergency condensers immersed in seawater. In case of a primary piping break, a two-train safety injection system is actuated. Each train includes a core makeup tank, an accumulator and a safety tank at low pressure. To assess the capability of these features to remove residual heat, the reactor and its safety systems have been modelled using thermal-hydraulics code ATHLET with conservative assumptions. The results of simulated transients for three typical PWR accidents are presented: a turbine trip with station black out, a large break loss of coolant accident and a small break loss of coolant accident. The analyses show that the safety criteria are respected and that the reactor quickly reaches a safe shutdown state without operator action and external power. (authors)
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. 2335-2344
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
- 49005032
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- A CODES; COMPUTERIZED SIMULATION; LOSS OF COOLANT; LOSS OF FLOW; PWR TYPE REACTORS; REACTOR ACCIDENT SIMULATION; REACTOR SAFETY; TRANSIENTS; UNDERWATER FACILITIES
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 11 refs.; This record replaces 48095427