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NUCLEAR DESIGN STUDY ON A SUPER HIGH-BURNUP FUEL ASSEMBLY FOR PRESSURIZED WATER REACTORS USING TRANSURANIUM

机译:铀用于加压水反应器的超高燃分燃料组件的核设计研究

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A conceptual design study nas carried out on a super high-burnup mixed-oxide (MOX) fuel assembly (SHB FA) for pressurized water reactors (PWRs) using transuranium (TRU). This-study aims to avoid the surplus plutonium (Pu) accumulation and to reduce the accumulation of long-lived-radioactive minor actinides (MAs) by utilizing the currently existing PWRs under the condition that the Japanese program to develop fast breeder reactors (FBRs) is tend to delay. For this purpose, an SHE FA with discharged burnup of similar to 80 GWd/t was investigated bu utilizing MAs positively as both burnable absorbers and fissile suppliers and loading high-content Pu. It is possible to load the SHE FAs in a current PWR together with UO2 FAs and to use 2.5 times as much amount of Pu as that in a standard 1/3 MOX core. Moreover, it is found to be possible to reduce the total number of fresh FAs further from that of a high-burnup (55 GWd/t in maximum) UO2 (4.9 wt%) core and also to reduce the accumulation of MAs in the nuclear fuel cycle significantly. [References: 7]
机译:对使用超铀(TRU)的压水堆(PWR)的超高燃混合氧化物(MOX)燃料组件(SHB FA)进行了概念设计研究。本研究的目的是在日本计划开发快速增殖反应堆(FBR)的条件下,通过利用当前存在的PWR来避免过量的((Pu)积累并减少长寿命放射性次minor系元素(MAs)的积累。往往会延迟。为此,积极研究了MAs作为可燃吸收剂和易裂变供应商,并装载了高含量的Pu,研究了燃尽量接近80 GWd / t的SHE FA。可以将SHE FA和UO2 FA一起加载到当前PWR中,并且使用的Pu量是标准1/3 MOX内核中的2.5倍。此外,发现有可能从高燃尽(最大55 GWd / t)UO2(4.9重量%)核中减少新鲜FA的总数,并减少核中MA的积累燃油循环明显。 [参考:7]

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