| Issue |
EPJ Web Conf.
Volume 153, 2017
ICRS-13 & RPSD-2016, 13th International Conference on Radiation Shielding & 19th Topical Meeting of the Radiation Protection and Shielding Division of the American Nuclear Society - 2016
|
|
|---|---|---|
| Article Number | 05006 | |
| Number of page(s) | 7 | |
| Section | 5. Fission Facilities, Fuel Cycle & Waste Management Facilities, Decommissioning | |
| DOI | https://doi.org/10.1051/epjconf/201715305006 | |
| Published online | 25 September 2017 | |
https://doi.org/10.1051/epjconf/201715305006
Reflector and Protections in a Sodium-cooled Fast Reactor: Modelling and Optimization
CEA, DEN/DER, F-13108 Saint-Paul-lez-Durance, France
a Corresponding author: david.blanchet@cea.fr
Published online: 25 September 2017
The ASTRID project (Advanced Sodium Technological Reactor for Industrial Demonstration) is a Generation IV nuclear reactor concept under development in France [1]. In this frame, studies are underway to optimize radial reflectors and protections. Considering radial protections made in natural boron carbide, this study is conducted to assess the neutronic performances of the MgO as the reference choice for reflector material, in comparison with other possible materials including a more conventional stainless steel. The analysis is based upon a simplified 1-D and 2-D deterministic modelling of the reactor, providing simplified interfaces between core, reflector and protections. Such models allow examining detailed reaction rate distributions; they also provide physical insights into local spectral effects occurring at the Core-Reflector and at the Reflector-Protection interfaces.
© The Authors, published by EDP Sciences, 2017
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 4.0, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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