The core design of ALFRED, a demonstrator for the European lead-cooled reactors

核工程 核反应堆堆芯 热工水力学 瞬态(计算机编程) 限制 芯(光纤) 欧洲联盟 铅(地质) 紧急停堆 机械工程 工程类 计算机科学 物理 机械 传热 地质学 地貌学 业务 操作系统 经济政策 电信
作者
Giacomo Grasso,C. Petrovich,Davide Mattioli,C. Artioli,Pierre Sciora,Daniela Gugiu,G. Bandini,E. Bubelis,Konstantin Mikityuk
出处
期刊:Nuclear Engineering and Design [Elsevier BV]
卷期号:278: 287-301 被引量:167
标识
DOI:10.1016/j.nucengdes.2014.07.032
摘要

The European Union has recently co-funded the LEADER (Lead-cooled European Advanced DEmonstration Reactor) project, in the frame of which the preliminary designs of an industrial size lead-cooled reactor (1500 MWth) and of its demonstrator reactor (300 MWth) were developed. The latter is called ALFRED (Advanced Lead-cooled Fast Reactor European Demonstrator) and its core, as designed and characterized in the project, is presented here. The core parameters have been fixed in a comprehensive approach taking into account the main technological constraints and goals of the system from the very beginning: the limiting temperature of the clad and of the fuel, the Pu enrichment, the achievement of a burn-up of 100 GWd/t, the respect of the integrity of the system even in design extension conditions (DEC). After the general core design has been fixed, it has been characterized from the neutronic point of view by two independent codes (MCNPX and ERANOS), whose results are compared. The power deposition and the reactivity coefficient calculations have been used respectively as input for the thermal-hydraulic analysis (TRACE, CFD and ANTEO codes) and for some preliminary transient calculations (RELAP, CATHARE and SIM-LFR codes). The results of the lead activation analysis are also presented (FISPACT code). Some issues of the core design are to be reviewed and improved, uncertainties are still to be evaluated, but the verifications performed so far confirm the promising safety features of the lead-cooled fast reactors.
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