Conveners
5.2 Advanced Fast Reactor Fuel Development II
- Mikhail Veshchunov (IAEA)
- Victor BLANC (French Atomic Energy Commission)
Mr
E. Vázquez
(National Atomic Energy Commission of Argentina (CNEA)), Mr
Osvaldo Azpitarte
(National Atomic Energy Commission of Argentina (CNEA))
26/06/2017, 15:10
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
The International Atomic Energy Agency (IAEA) recently established a Coordinated Research Project (CRP) on “Sodium Properties and Safe Operation of Experimental Facilities in Support of the Development and Deployment of Sodium-cooled Fast Reactors - NAPRO”, to be carried out in the period 2013 – 2017.
Eleven institutions from ten Member States participate in this CRP.
The complete scope of...
Mr
Stephane Vaudez
(CEA)
26/06/2017, 15:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
In order to prepare the industrial deployment of Sodium Fast Reactor (SFR), a French prototype is envisaged for 2025 (ASTRID: Advanced Sodium Technological Reactor for Innovative Demonstration). Its MOX (mixed oxide) fuels will be produced by a new industrial facility, currently under development and named AFC (for “Atelier de Fabrication des Coeurs”, core fabrication facility).
The...
Dr
Victor BLANC
(CEA)
26/06/2017, 15:50
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
In the framework of the Basic Design of the Advanced Sodium Technological Reactor for Industrial Demonstration (ASTRID) project, the design margins have to be defined with accuracy. The design criterion considered here is the fuel melting margin during nominal operation conditions, which is given by the melting probability.
Oxide fuel temperature and melting temperature being calculated with...
Dr
Kamil Tucek
(European Commission, Joint Research Centre)
26/06/2017, 16:10
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
In order to develop the fast neutron systems, three prototypes of the Sodium Fast Reactor, the Gas-cooled Fast Reactor and a heavy liquid metal cooled Accelerator Driven System are studied in Europe: ASTRID (SFR prototype), ALLEGRO (GFR prototype) and MYRRHA (LBE-cooled ADS system related to the ALFRED LFR-demonstrator). The ESNII+ project with its workpackage 7-FUEL SAFETY aims to provide a...
Mr
Suresh Kumar Kannankara Vasudevan
(IGCAR, Dept. of Atomic Energy, India)
26/06/2017, 16:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
The advantages of a fast reactor, especially one that uses Uranium-Plutonium Carbide as its fuel is well documented. Irradiation performance assessment of carbide fuels began with experimental irradiations in EBR-II, FFTF, HFR, Rapsodie and Phenix etc. India has the extensive experience with this type of fuel at the Fast Breeder Test Reactor at Kalpakkam that has been operating for over 25...
Mr
Sergey Porollo
(IPPE)
26/06/2017, 16:50
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
Uranium mononitride fuel was used in the fourth and fifth BR-10 reactor core loadings. The total number of irradiated fuel pins was 1250 (660 and 590 fuel pins in fuel loadings IV and V respectively). Most fuel pins were irradiated up to design burnup (8%) without cladding failure.
In addition to standard FAs, some experimental FAs were irradiated in BR-10 reactor. The post irradiation...
