Conveners
Panel 1: Development and Standardization of Safety Design Criteria (SDC) and Guidelines (SDG) for Sodium Cooled Fast Reactors
- Vladimir Kriventsev (IAEA)
Dr
Yasushi OKANO
(Japan Atomic Energy Agency)
26/06/2017, 17:35
Panel 1: Development and standardization of Safety Design Criteria and Guidelines for Sodium Cooled Fast Reactors
ORAL
The Generation-IV International Forum (GIF) Task Force completed development of Safety Design Criteria (SDC) for the Generation-IV SFR systems in May, 2013. SDC reflects high level GIF safety and reliability goals (excellence in operational safety and reliability, and reduced likelihood and degree of core damage) and follows GIF basic safety approach (application of defense-in-depth and...
Mr
Ryodai Nakai
(Japan Atomic Energy Agency)
26/06/2017, 17:45
Panel 1: Development and standardization of Safety Design Criteria and Guidelines for Sodium Cooled Fast Reactors
ORAL
The Generation-IV International Forum (GIF) Safety Design Criteria Task Force (SDC TF) has been developing a set of safety design guidelines (SDG) to support practical application of SDC since completion of the “SDC Phase I Report” that clarifies safety design requirements for Generation IV SFR systems. The main objective of the SDG development is to assist SFR developers and vendors to...
Mr
Paul Gauthé
(CEA)
26/06/2017, 17:55
Panel 1: Development and standardization of Safety Design Criteria and Guidelines for Sodium Cooled Fast Reactors
ORAL
From a general perspective, generation IV (GEN IV) reactors should excel in safety, and as part of a continuous improvement process, provide safety enhancements with respect to GENIII reactors.
GENIII safety objectives are already very ambitious, notably regarding:
- Prevention of the severe accident;
- Mitigation of the severe accident in the frame of the fourth level of defense in...
Mr
Subhash Chander CHETAL
(India)
26/06/2017, 18:05
Panel 1: Development and standardization of Safety Design Criteria and Guidelines for Sodium Cooled Fast Reactors
ORAL
to be provided later by the author
Dr
JAEWOON YOO
(Korea Atomic Energy Research Institute)
26/06/2017, 18:15
Panel 1: Development and standardization of Safety Design Criteria and Guidelines for Sodium Cooled Fast Reactors
ORAL
Korea Atomic Energy Research Institute (KAERI) is developing Prototype Generation-IV SFR (PGSFR). The first design stage has been completed at the end of 2015 and the preliminary safety information document (PSID) has been issued as a main outcome of the phase. The safety design approach of PGSFR is compliance of defense-in-depth and to enhance the inherent and passive safety design features...
Iurii Ashurko
(IPPE)
26/06/2017, 18:25
Panel 1: Development and standardization of Safety Design Criteria and Guidelines for Sodium Cooled Fast Reactors
