Nitride fuel for Gen IV nuclear power systems

被引:55
作者
Ekberg, Christian [1 ]
Costa, Diogo Ribeiro [2 ,3 ]
Hedberg, Marcus [1 ]
Jolkkonen, Mikael [2 ]
机构
[1] Chalmers, Nucl Chem Ind Mat Recycling, Gothenburg, Sweden
[2] Kungliga Tekn Hgsk, Div Nucl Engn, Stockholm, Sweden
[3] Westinghouse Elect Sweden AB, Vasteras, Sweden
关键词
Nuclear fuel; Nitride nuclear fuels; Gen IV; Production of nitrides; Nuclear fuel recycling; Dissolution of nitrides; CARBOTHERMIC SYNTHESIS; URANIUM MONONITRIDE; SOL-GEL; VAPORIZATION BEHAVIOR; OXIDATIVE AMMONOLYSIS; NITROGEN; FABRICATION; MONOCARBIDE; REDUCTION; KINETICS;
D O I
10.1007/s10967-018-6316-0
中图分类号
O65 [分析化学];
学科分类号
070302 ; 081704 ;
摘要
Nuclear energy has been a part of the energy mix in many countries for decades. Today in principle all power producing reactors use the same techniqe. Either PWR or BWR fuelled with oxide fuels. This choice of fuel is not self evident and today there are suggestions to change to fuels which may be safer and more economical and also used in e.g. Gen IV nuclear power systems. One such fuel type is the nitrides. The nitrides have a better thermal conductivity than the oxides and a similar melting point and are thus have larger safety margins to melting during operation. In addition they are between 30 and 40% more dense with respect to fissile material. Drawbacks include instability with respect to water and a sometimes complicated fabrication route. The former is not really an issue with Gen IV systems but for use in the present fleet. In this paper we discuss both production and recycling potential of nitride fuels.
引用
收藏
页码:1713 / 1725
页数:13
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