Conveners
3.1 Safety Program
- Pavel Alekseev (NRC “Kurchatov Institute”)
- Andrei Rineiski (Karlsruhe Institute of Technology (KIT))
Prof.
Koji Morita
(Kyushu University)
26/06/2017, 13:00
Track 3. Fast Reactor Safety
ORAL
This paper describes the status of safety research activity in the field of sodium-cooled fast reactors (SFRs) in Japan, mainly on severe accident related issues. Core damage sequences are analyzed by applying probabilistic risk assessment methodology and categorized into typical accident phases, i.e., initiating phase, transitions phase, and material relocation and cooling phase. In order to...
Dr
Alfredo Vasile
(CEA)
26/06/2017, 13:20
Track 3. Fast Reactor Safety
ORAL
The Generation IV (GEN-IV) international forum is a framework for international cooperation in research and development (R&D) for the next generation of nuclear energy systems. Concerning the sodium-cooled fast reactor (SFR) system, there are five cooperation projects for R&D. The SFR Safety and Operation (SO) project addresses the area of the safety technology and the reactor operation...
Mr
Stéphane BEILS
(AREVA NP)
26/06/2017, 13:40
Track 3. Fast Reactor Safety
ORAL
ASTRID is the Advanced Sodium Technological Reactor for Industrial Demonstration which is intended to prepare the Generation IV reactor, with improvements in safety and operability. In order to meet the objectives of the 4th generation reactors and comply with the related specifications, the ASTRID project integrates innovative options.
In the earlier phase of ASTRID project, a specific...
Mr
Artem Anfimov
(Joint Stock Company "Afrikantov Experimental Design Bureau for Mechanical Engineering")
26/06/2017, 14:00
Track 3. Fast Reactor Safety
ORAL
Safety analysis of BN-1200 RP Unit is performed with account of requirements specified for innovative nuclear technologies including IAEA recommendations.
The following BDBAs are considered within BN-1200 project:
Heat removal accidents with loss of energy supply, failures of active systems for reactor shutdown, failures of normal cooldown system and active components of emergency...
Mr
Frédéric Payot
(CEA : Commissariat à l’Energie Atomique et aux Energies Alternatives)
26/06/2017, 14:20
Track 3. Fast Reactor Safety
ORAL
The CEA, together with the NNC, has carried out a feasibility study with regard to conducting an in-pile test program - the future SAIGA program (Severe Accident In-pile experiments for Gen-IV reactors and the Astrid prototype) - on the degradation of an ASTRID-like fuel in the IGR reactor (Impulse Graphite Reactor operated by NNC). The purpose of the SAIGA program is to qualify the SIMMER...
Mr
Shigenobu Kubo
(Japan Atomic Energy Agency)
26/06/2017, 14:40
Track 3. Fast Reactor Safety
ORAL
This paper describes safety design concept for future sodium-cooled fast reactors (SFRs) in Japan, which is based on the safety design criteria and safety design guidelines under development in the international forum of generation IV nuclear energy systems. The future safety design of SFRs should be advanced taking the feedback of experiences, achievement of existing technology, and...
