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Plutonium isotopic composition of high burnup spent fuel discharged from light water reactors

机译:从轻水反应堆排放的高燃耗乏燃料中的iso同位素组成

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摘要

The isotopic composition and amount of plutonium (Pu) in spent fuel from a high burnup boiling water reactor (HB-BWR) and a high burnup pressurized water reactor (HB-PWR), each with an average discharge burnup of 70 GWd/t, were estimated, in order to evaluate fast breeder reactor (FBR) fuel composition in the transition period from LWRs to FBRs. The HB-BWR employs spectral shift rods and the neutron spectrum is shifted through the operation cycle. The weight fraction of fissile plutonium (Puf) isotopes to the total plutonium in HB-BWR spent fuel after 5 years cooling is 62%, which is larger than that of conventional BWRs with average burnup of 45 GWd/t, because of the spectral shift operation. The amount of Pu produced in the HB-BWR is also larger than that produced in a conventional BWR. The HB-PWR uses a wider pitch 17 × 17 fuel rod assembly to optimize neutron slowing down. The Puf fraction of HB-PWR spent fuel after 5 years cooling is 56%, which is smaller than that of conventional PWRs with average burnup of 49 GWd/t, mainly because of the wider pitch. The amount of Pu produced in the HB-PWR is also smaller than that in conventional PWRs.
机译:来自高燃耗沸水反应堆(HB-BWR)和高燃耗压水反应堆(HB-PWR)的乏燃料中each的同位素组成和amount的含量,它们的平均燃耗为70 GWd / t,进行了估算,以评估从轻水堆到轻水堆过渡期的快速增殖反应堆(FBR)燃料成分。 HB-BWR采用谱移棒,中子谱在整个工作周期内发生移动。冷却5年后,HB-BWR乏燃料中易裂变lu(Puf)同位素占总p的重量分数为62%,这比平均燃耗为45 GWd / t的常规BWR大,这是由于光谱偏移操作。 HB-BWR中产生的Pu量也大于常规BWR中产生的Pu量。 HB-PWR使用宽节距17×17燃料棒组件来优化中子减速。冷却5年后,HB-PWR乏燃料的Puf分数为56%,比平均燃耗为49 GWd / t的传统PWR的Puf分数要小,这主要是因为沥青较宽。 HB-PWR中产生的Pu量也小于常规PWR中的Pu量。

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