Conveners
5.10 Fuel Modeling and Simulation
- Mikhail Veshchunov (IAEA)
- Marc LAINET (French Alternative Energies and Atomic Energy Commission (CEA))
Mr
Evgenii Marinenko
(Institute for Physics and Power Engineering)
27/06/2017, 13:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
The main life limiting factor of nitride fuel pins at high burn-up is fuel cladding mechanical interaction (FCMI) leading to strong deformation or even cladding destruction. The consequences of FCMI depend on fuel and cladding swelling rates, cladding creep rate, cladding long-term stress rupture etc. The calculation modelling problem arise from not enough data on nitride out-of-pile...
Dr
bruno MICHEL
(CEA/DEN/DEC/SESC/LSC)
27/06/2017, 13:50
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
In the framework of the basic design of ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) the GERMINAL fuel performance code is developed in the PLEIADES software environment. In order to improve one dimensional modelling of GERMINAL, a 3D simulation for the SFR fuel pin behavior under irradiation has been proposed.
The 3D model represents a single pellet fragment...
Mr
Marc LAINET
(French Alternative Energies and Atomic Energy Commission (CEA))
27/06/2017, 14:10
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
A fuel performance code for SFR oxide fuel pins, GERMINAL, is developed by CEA within the PLEIADES simulation framework. The present main goal of GERMINAL is to meet the needs of the design studies of ASTRID, the future Advanced Sodium Technological Reactor for Industrial Demonstration in France.
Recent works have been conducted to improve the modelling of different physical mechanisms...
Mr
Andrey Boldyrev
27/06/2017, 14:30
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
The advanced version of code BERKUT designed for mechanistic modelling of oxide and nitride single fuel rod behavior under normal and accidental conditions of liquid metal cooled fast reactor operation, is under development at IBRAE RAN during the last five years in frame of “Codes of new generation” project included into the “BREAKTHROUGH” (or “PRORYV”) project. The code models are grounded...
Prof.
Iulian Golovchenko
(Russian Federation)
27/06/2017, 14:50
Track 5. Fast Reactor Materials (Fuels and Structures) and Technology
ORAL
To guarantee an inherent safety in advanced BN-reactors the breeding ratio of its active core (BRC) must have the meaning of BRC ≥ 1,0. It could be reached in heterogeneous oxide-metal cores of various types in use of metal uranium as the fertile components in the proportion of MOX:U ≈ 2:1.
We obtained the experience of manufacturing the fertile columns of various types from the metal...
