Description
Chairperson: Anthony BONFRATE
M.
Abdullah ABUDRA'A
(CEA)
09/05/2016 17:00
Nuclear Physics
Oral Presentation
Contact radiotherapy by X-Rays generator is a cancer treatment technique using low energy X-Rays (≤ 50 keV). This technique became more reliable after the latest evolutions of the X-Ray tubes, and hence, led to the development of new treatment devices, such as INTRABEAM® and Papillon 50®. The irradiation is done in contact with the tumor so it receives a high dose while preserving neighboring...
Mme
Alice Somaini
(doctorante)
09/05/2016 17:15
Nuclear Physics
Oral Presentation
Monte Carlo codes are often used in nuclear reactor simulations to realize fuel evolutions as a function of time, in order to know the spent fuel composition at the end of the irradiation cycle.
The evolution of the entire reactor core is not possible with stochastic codes, because of the source convergence problem and the too costly machine time required.
So, a simple reactor model is...
Mlle
Yara Haddad
(CSNSM, Univ Paris-Sud)
09/05/2016 17:30
Nuclear Physics
Oral Presentation
This Ph.D. study is concerned with the UO2 nuclear spent fuel. A high burnup structure (HBS, also so-called rim structure) is observed with a typical thickness of 100 to 200 µm at the peripheral region of the nuclear fuel pellets. Several observations and characterizations are notable in that zone [1-5]:
1- An increase of Pu content and burnup.
2- The development of fission gas pores...
M.
Mathieu Muniglia
(CEA)
09/05/2016 17:45
Nuclear Physics
Oral Presentation
In the actual context of energetic transition, the increase of the renewable energies contribution (as wind farms, solar energy, or biomass) is a major issue. For example, the part of intermittent renewable energies is forecast to be around 30% of the total production in 2030, against 6% today. On the other hand, their intermittent production may lead to an important imbalance between...
Mlle
Gabriela DURAN-KLIE
(IPNO)
09/05/2016 18:00
Nuclear Physics
Oral Presentation
The molten salt fast reactor (MSFR) is an innovating concept of the molten salt reactor (MSR) developed by CNRS (France) since 2004. This reactor is designed for the use of a liquid nuclear adapted to work under Thorium fuel cycle (Th232-U233). The nuclear fuel retained for the MSFR will be composed for the fluoride molten salt mixture, LiF-ThF4-(UF4-UF3) (77–19–4) mol%. A current subject in...