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HEMERA: a 3D coupled core-plant system for accidental reactor transient simulation

机译:Hemera:用于意外反应堆瞬态模拟的3D耦合核心植物系统

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A Nuclear Power Supply System (NPSS) is driven and regulated by several diversified and complex phenomena which are distributed in space and coupled in time in different and somewhat varying ways. In a first approximation, they depend on the reactor type, the core design and lay-out, the fuel features, the coolant, the loading strategy and cycle, the operating mode and, more generally, on the whole status of the system. The main coupling agent in a reactor system is the temperature field inside the fuel, the core and its immediate surroundings. The temperature affects the neutron behaviour, both in normal operation and during transients, through the cross-sections, which account for the probability of neutrons to interact with matter in every zone and at any time. Thus, temperature is always relevant to normal reactor operation and control, but it may become extremely important and sometime decisive in the transients, mainly the reactivity driven ones, which are characterized by very short response-time and severe power variations. In the framework of their collaboration to develop a system to study reactor transients in "safety-representative conditions", IRSN and CEA have launched the development of a fully coupled 3D computational chain, called HEMERA (Highly Evolutionary Methods for Extensive Reactor Analyses), based on the French SAPHYR code system, composed by APOLLO2, CRONOS2 and FLICA4 codes, and the system code CATHARE. It includes cross sections generation, steady-state, depletion and transient computation capabilities in a consistent approach. Multi-level and multi-dimensional models are developed to account for neutronics, core thermal-hydraulics, fuel thermal analysis and system thermal-hydraulics. Currently Control Rod Ejection (RIA) and Main Steam Line Break (MSLB) accidents are investigated. The HEMERA system is presently applied to French PWR. The present paper outlines the main physical phenomena to be accounted for in such a coupled computational chain with significant time and space effects. A selection of results is presented along with a comparison of the available levels of simulation, ranging from 0D to 3D and from assembly-wise to pin-wise in the core.
机译:甲核供电系统(NPSS)由分布在空间和耦合在时间上不同而有所不同的方式几个多样化和复杂的现象驱动和调节。在第一近似中,它们取决于反应器类型,芯设计及布局,燃料的功能,在冷却剂中,加载策略和周期,操作模式,并且更一般地,在系统的整个状态。在一个反应​​器系统中的主要偶联剂是燃料,芯和其周围的环境中的温度场。温度影响中子的行为,无论是在正常运行和过渡阶段,通过横截面,占中子的概率在每个区域,并随时与物质相互作用。因此,温度始终相关与正常反应器操作和控制,但也可以成为在瞬变,主要的反应性驱动的,其特征为非常短的响应时间和严重的功率变化极其重要和决定性的某个时候。在他们合作开发一个系统来研究反应堆瞬变“安全代表条件”的框架内,IRSN和CEA都推出了完全耦合的三维计算链的发展,被称为HEMERA(高度进化的方法进行广泛的反应堆分析),基于在法国SAPHYR代码系统中,通过APOLLO2,CRONOS2和FLICA4代码和系统代码CATHARE组成。它包括横截面产生,稳定状态,消耗和一致的方法瞬时计算能力。多层次,多维度模型的开发,以占中子,核热工水力学,热燃油分析和系统热工水力学。目前控制棒抛射(RIA)和主蒸汽管破裂(MSLB)事故进行调查。该HEMERA系统目前应用于法国压水堆。本文件概括了应占在这种加上显著时间和空间效应计算链中的主要的物理现象。结果的选择被呈现随着仿真的可用水平的比较,从0D至3D和从组件方式对销明智在芯。

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