Reflector and Protections in a Sodium-cooled Fast Reactor: Modelling and Optimization

被引：5
|
作者：
Blanchet, David [1 ]
Fontaine, Bruno [1 ]
机构：
[1] CEA, DEN DER, F-13108 St Paul Les Durance, France
来源：
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 | 2017年 / 153卷
关键词：
D O I：
10.1051/epjconf/201715305006
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
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.
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页数：7
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