输运堆芯的快速初步建模

V. Korolev
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引用次数: 0

摘要

目前,JSC Baltiskiy zavod已经建造并运输到Pevek Akademik Lomonosov的部署地点,一个浮动核电机组(FNPU),项目20870。还有三艘22220项目(北极、西伯利亚、乌拉尔)的多用途核破冰船正在波罗的海建造,处于不同的准备阶段。已经决定建造一艘更大功率的核动力破冰船Lider。由JSC OKBM Afrikantov开发的整体反应堆安装在核破冰船上,使用新的装配式堆芯,这种堆芯以前没有在浮式设施中使用过。要使这些核具有尽可能有利的特性,需要进行大量的初步计算。本文提出了一种具有不同工作特性和设计特性的浮式岩心快速建模方法。这个过程可以作为初步建模的一部分。该程序是基于使用作者在(Korolev 2009)中提出的组合无量纲参数。提出了一种基于核反应堆核电厂的浮物堆芯关键性能模型。分析了可安装在模块化或整体设计的运输堆中的8种组合型堆芯方案。
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Rapid preliminary modeling of transport reactor cores
At the present time, JSC Baltiskiy zavod has built and transported to the deployment site at Pevek Akademik Lomonosov, a floating nuclear power unit (FNPU), project 20870. There are also three multi-purpose nuclear icebreakers of project 22220 (Arktika, Sibir, Ural) under construction at Baltiskiy being at different readiness stages. A decision has been made to build a nuclear icebreaker, Lider, of even a higher power. Integral reactors developed by JSC OKBM Afrikantov are installed in the nuclear icebreakers using new assembly-type cores which have not been used earlier in floating facilities. A great deal of preliminary calculation is required to give these cores as advantageous characteristics as possible. The paper proposes a procedure for rapid modeling of floating cores with varied operating and design characteristics. This procedure can be used as part of preliminary modeling. The procedure is based on using a combined dimensionless parameter proposed by the author in (Korolev 2009). A chart is presented to model the key performance of cores for floating objects with a nuclear reactor NPPs. Eight assembly-type core options, which can be installed in transport reactors of a modular or integral design, are analyzed.
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