【摘要】 根据钍-铀混合氧化物燃料在高温气冷堆核电站示范工程(HTR-PM)框架下的中子学与瞬态事故特性,基于铀原子份额和燃料碳/重金属比例2种参数的参数分析,寻找混合氧化物(MOX)装载的优化方案。分析结果表明,随着碳/重金属比例的减小,单位产能对应的天然铀需求量降低,同时以失冷失压事故后燃料温度为代表的安全特性参数都逐渐恶化;最优化方案相比于HTR-PM实际燃料装载方案,可节省约8.5%的U3O8需求量[~20 kg/(GW·d)];同时混合氧化物方案对钍燃料的利用率很低,仅为6%左右,必须进一步探索提高钍燃料在线利用率的途径。更多还原

【Abstract】 The neutronics and accidental features of HTR-PM with Th-U-MOX fuel loading are investigated. The parametric analysis is performed on the uranium fraction in MOX fuel and the C/HM ratio, for the optimization of Th-U-MOX loading. It is revealed that the requirement of natural uranium per energy production decreases when the C/HM ratio decreases. The optimized scheme reduces the uranium requirement for 8.5% and provides thorium utilization as low as 6%.更多还原