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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。
Based on the neutron and transient characteristics of thorium-uranium mixed oxide fuel (HTR-PM) under HTR-PM nuclear power plant project, based on the parameter analysis of two parameters of uranium atomic percentage and fuel carbon / heavy metal ratio, Looking for a mixed oxide (MOX) loading optimization. The results show that with the decrease of carbon / heavy metal ratio, the demand of natural uranium corresponding to unit production capacity decreases, while the safety characteristic parameters such as fuel temperature after the loss of cold loss pressure are gradually deteriorated. Compared with the optimization scheme HTR-PM actual fuel loading scheme can save about 8.5% of U3O8 demand [~ 20 kg / (GW · d)]; meanwhile, the utilization of mixed-oxide solution for thorium fuel is very low, only about 6% Further explore ways to improve on-line utilization of thorium fuel.