双组份核电系统中钚成本问题研究

V. Dekusar, O. Gurskaya
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引用次数: 1

摘要

本文描述了一种可能的方法来计算热堆和快堆双组份核电系统的快堆中产生的钚的具体现值。这是考虑到,如果用以核电站生产的钚为原料的mox燃料的快堆代替热反应堆,以市场价格出售释放的天然铀,可以获得额外的收入。同时,在出售天然铀的同时,可以考虑按市场价值出售以天然铀为基础生产的其他产品,例如浓缩铀或热反应堆燃料组件。得到了所考虑的核反应堆的主要燃料特性与表征核反应堆效率的经济参数和核电厂燃料循环之间的关系。利用本文所描述的方法,对含商用钠高功率快堆和VVER-1200堆的双产品核电模型中钚的比现值进行了计算研究。在所有考虑的情况下的计算结果都表明钚的现值非常大。钚的获得成本(最终以钚和铀的能量当量为基础)与钚的成本(以燃料循环后端(从SNF提取钚)的成本为基础)的比较表明,即使在现有的铀价格下,关闭燃料循环的经济效率也是如此。
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ON THE ISSUE OF PLUTONIUM COST IN A TWO-COMPONENT NUCLEAR POWER SYSTEM
A possible approach to accounting for the specific present value of plutonium produced in fast reactors of a two-component nuclear power system (NPS) with thermal and fast reactors is described. The approach is based on taking into account the additional income that can be obtained by selling at the market price the natural uranium released when thermal reactors are replaced with fast reactors with MOX-fuel based on plutonium produced in NPS. At the same time, along with the sale of natural uranium, the sale at market value of other products made on its basis, for example, enriched uranium or fuel assemblies for a thermal reactors, can be considered. Relations between the main fuel characteristics of the considered nuclear reactors and the economic parameters characterizing the efficiency of nuclear reactors and the fuel cycle of a NPS are obtained. Using the methodology described in this paper, a computational study of the specific present value of plutonium in a two-product nuclear power model with commercial sodium high-power fast reactor and VVER-1200 reactors was carried out. The calculation results in all considered cases indicate very significant present value of plutonium. Comparison of the obtained cost of plutonium, which is ultimately based on the energy equivalent of plutonium and uranium, and the cost of plutonium, determined on the basis of the costs of the back-end of the fuel cycle (plutonium extraction from SNF), show the economic efficiency of closing the fuel cycle even at existing uranium prices.
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