Conveners
3.2 Core Disruptive Accident
- Andrey VOLKOV
- Koji Morita (Kyushu University)
Frédéric BERTRAND
(CEA Cadarache)
26/06/2017, 15:10
Track 3. Fast Reactor Safety
ORAL
The ASTRID reactor developed by the CEA with its industrial partners, will be used for demonstration of the safety and operability, at the industrial scale, of sodium fast reactors of the 4th generation. Among the goals assigned to ASTRID, one is to improve the safety and the reliability of such reactor (compared to previous sodium-cooled fast reactors). Among the innovations promoted in the...
Dr
Vladimir Kriventsev
(IAEA)
26/06/2017, 15:30
Track 3. Fast Reactor Safety
ORAL
Due to the inherent characteristics and robust design of Sodium cooled Fast Reactors (SFR), the core disruptive accident (CDA) is considered a very unlikely event. Nevertheless, to confirm the safety of the reactor, one of the hypothetical scenarios arising from the loss of coolant flow coupled with the failure of the shutdown system, referred to as the Unprotected Loss of Flow (ULOF) accident...
Mr
Seok-Hun Kang
(KAERI)
26/06/2017, 15:50
Track 3. Fast Reactor Safety
ORAL
The SAS4A safety analysis code, originally developed for the analysis of postulated Severe Accidents in Oxide Fuel Sodium Fast Reactors (SFR), has been significantly extended to allow the mechanistic analysis of severe accidents in Metallic Fuel SFRs. The new SAS4A models track the evolution and relocation of multiple fuel and cladding components during the pre-transient irradiation and during...
Dr
Velusamy Karuppanna Gounder
(IGCAR)
26/06/2017, 16:10
Track 3. Fast Reactor Safety
ORAL
The heat generating fuel pins in Sodium cooled Fast Reactors (SFR) are arranged in a tightly packed triangular pitch within a hexagonal sheath forming a fuel subassembly (SA). Due to the compact design, formation of local flow blockage inside the SA is possible. Such blockages are expected to grow gradually and the core monitoring thermocouples which are located at the top of the SA are...
Dr
Barbara Vezzoni
(Karlsruhe Institute of Technology (KIT)), Mr
MIchael Flad
(Karlsruhe Institute of Technology)
26/06/2017, 16:30
Track 3. Fast Reactor Safety
ORAL
The analyses of Hypothetical Core Disruptive Accidents (HCDAs) play a fundamental role in the safety assessment of Sodium Fast Reactors (SFRs). The accident sequence is subdivided into different phases suggested by dominant key phenomena. The Initiation Phase (IP) describes the fatal deviation from nominal operation until the failure of single sub-assemblies (SAs), while the subsequent...
Dr
KWI LIM LEE
(KAERI)
26/06/2017, 16:50
Track 3. Fast Reactor Safety
ORAL
KAERI (Korea Atomic Energy Research Institute) has been developing a preliminary specific design of the PGSFR (Prototype Gen-IV Sodium-cooled Fast Reactor), which is a pool-type sodium cooled fast reactor with a thermal power of 392.2 MW. The PGSFR has an inherent safety characteristic owing to the design to have a negative power reactivity coefficient during all operation modes and it has a...
