Neutronic investigation of ALFRED lead-Cooled fast reactor core using monte carlo modeling

被引：0
|
作者：
Ganjaroodi, Saeed Zare [1 ]
Zarifi, Ehsan [2 ]
机构：
[1] Amirkabir Univ Technol, Energy & Phys Dept, Tehran, Iran
[2] Nucl Sci & Technol Res Inst, Reactor & Nucl Safety Res Sch, Tehran, Iran
来源：
ATOMIC ENERGY | 2023年 / 134卷 / 3-4期
关键词：
LFR; ALFRED; MCNPX; SuperMC; Neutronic; VALIDATION; SUPERMC;
D O I：
10.1007/s10512-024-01054-2
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：
A Lead-Cooled Fast Reactor (LFR) is one of the six advanced fourth-generation reactors that many countries have been interested in designing, constructing, or develop them in the world. ALFRED reactor design investigated in this paper has 125 (MW) electric power and is being cooled by lead. The main purpose of the ALFRED project is to design and construct a reactor with high safety performance and reliability in all operation modes. In the present study, Monte Carlo codes MCNPX and SuperMC are used to calculate the neutronic parameters of the ALFRED reactor core including effective multiplication factor, kinetic parameters, neutron flux, and power distribution based on the latest design data. According to the results, the insertion of the control rods into the core can move the maximum flux height of about 40% to 50% to the end. Also, comparing codes' results show an appropriate consistency.
引用
收藏
页码：264 / 274
页数：11
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