Conveners
3.6 Safety Analysis
- Yury Khomyakov (Private institution «Innovation and technology center for the «PRORYV» project»)
- Staffan Qvist (LeadCold AB)
Prof.
Akira Yamaguchi
(The University of Tokyo)
28/06/2017, 15:30
Track 3. Fast Reactor Safety
ORAL
The safety design criteria (SDC) has been established in the framework of the Generation-IV International Forum by incorporating safety-related R&D results on innovative technologies and lessons-learned from Fukushima Dai-ichi nuclear power plants accident in order to provide the set of general criteria for the safety designs of structures, systems and components of Generation-IV sodium-cooled...
Mr
CLEMENT RAVI CHANDAR SOWRINATHAN
(INDIRA GANDHI CENTRE FOR ATOMIC RESEARCH)
28/06/2017, 15:50
Track 3. Fast Reactor Safety
ORAL
To provide rapid growth and faster deployment of fast breeder reactors in future,
metal fuelled reactors are planned. The Design safety limits (DSL) for normal and anticipated
transient events are arrived at for a typical 500 MWe metal fuelled reactor, which is
addressed in this paper.
All the design basis events occurring during the lifetime of the components concerned
are classified...
Dr
Nikita Rtishchev
(IBRAE RAN), Mr
Ruslan Chalyy
(IBRAE RAN)
28/06/2017, 16:10
Track 3. Fast Reactor Safety
ORAL
The SOCRAT-BN integral code has been developed in frame of Federal Target Program «New-Generation Nuclear Power Technologies for the Period 2010–2015 and up to 2020». The code is intended for safety justification of NPPs with sodium-cooled reactors under DBA and BDBA including those that lead to core melting.
The modules integrated into SOCRAT-BN code allow to perform coupled simulation of...
Dr
Alfredo Vasile
(CEA)
28/06/2017, 16:30
Track 3. Fast Reactor Safety
ORAL
One of the key issues in the design of the Gen IV GFR ALLEGRO, a helium-cooled experimental fast reactor, is the core cooling in accident conditions, mainly due to the low thermal inertia of the coolant.
After a brief description of the reactor, this paper presents the currently adopted approach to decay heat removal, and the analysis of some of the most penalizing pressurized and...
Dr
Staffan Qvist
(LeadCold AB)
28/06/2017, 16:50
Track 3. Fast Reactor Safety
ORAL
The Autonomous Reactivity Control (ARC) system was developed to ensure inherent safety of fast reactors while having a minimal impact on reactor performance and economic viability. The ARC system is a modification to a standard fast reactor fuel assembly, in which two liquid-filled reservoirs, one above and one below the core, are connected by a tube which replaces one of the fuel rods in the...
Mr
Paul Gauthé
(CEA)
28/06/2017, 17:10
Track 3. Fast Reactor Safety
ORAL
Improvements on SFR design are expected to meet the safety goals of GEN IV reactors. One main objective is to enhance the core behavior during unprotected transients to increase the level of prevention of severe accidents. However, performing a detailed safety analysis for all initiators requires many multiphysical analyses and is a rather lengthy process when designers need to assess safety...
