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Simulation with SAS-SFR of a ULOF transient on ASTRID-like core and analysis of molten clad relocation dynamics in heterogeneous subassemblies with SAS-SFR

机译:用SAS-SFR仿真SAS-STRID核心的ULOF瞬态SAS-SFR的仿真与SAS-SFR的异构子组件中熔融包层搬迁动力学分析

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In the framework of the ASTRID project, CEA, AREVA and EDF are working together to build a robust safety demonstration for innovative Sodium Fast Reactors (SFR). The CFV concept is a low sodium voiding effect core designed by the CEA to improve the reactor behavior in case of accidental transients. Up to now, no evaluation of this core during the primary phase of the accident was available as soon as the core degradation begins. Indeed some elements led to think that the dedicated code SAS-SFR would not be able to deal with the axial heterogeneity of this core. This paper aims at evaluating SAS-SFR ability to simulate an unprotected loss of flow (ULOF) transient applied to the CFV core and to assess the advantages of this core during such a transient. No specific problem has been identified which could invalidate the use of SAS-SFR in such conditions during the simulation. In particular, it has been checked that conditions to form two separate molten cavities in a pin were not met in this transient. The behavior of the core during the transient in terms of boiling phenomenon and its feedback with neutron physics is the same as what was expected according to the experience gained at EDF R&D on radially heterogeneous cores with equivalent neutronic properties. Namely, the core partial dry-out does not induce any power excursion since the reactivity feedback resulting from boiling remains negative. A focus on clad relocation in the axially heterogeneous sub-assemblies has shown that the cold fertile plate inserted in the inner core could trap molten clad in the middle of the core and thus could lower the reactivity insertion due to clad movement in the primary phase of the accident. However, a parametric study on the main parameters involved indicates that clad relocation kinetics and the resulting reactivity effects are very sensitive to vapor friction factor and to the axial power profile of the subassembly. Therefore, these parameters and their effect on transients will be further investigated in the frame of the ASTRID project in order to consolidate the preliminary conclusions on core behavior issues.
机译:在Astrid项目的框架中,CEA,ISVA和EDF正在共同努力,为创新的快速反应器(SFR)构建强大的安全示范。 CFV概念是由CEA设计的低钠空隙效应核心,以改善意外瞬变的反应器行为。到目前为止,一旦核心退化开始,就无法在事故的主要阶段进行评估。实际上,一些元素导致专用代码SAS-SFR无法处理该核心的轴向异质性。本文旨在评估SAS-SFR的能力,以模拟应用于CFV核心的未受保护的流动损失(ULOF)瞬态的能力,并在这种瞬态期间评估该核心的优势。没有识别出特定的问题,这可以使SAS-SFR在仿真过程中的使用中无效。特别地,已经检查了在该瞬态中不满足在销中形成两个单独的熔融腔的条件。核心在沸腾现象的瞬态中的行为及其与中子物理学的反馈与在径向异质核上在具有等同中性性质的径向异质核上获得的经验相同。即,由于沸腾导致的反应性反馈保持负面,因此核心部分干式输出不会诱导任何功率偏移。聚焦在轴向异构子组件包重新定位已经表明,插入内芯的冷育板可陷阱熔融包覆在芯的中间,从而可降低反应性引入由于包层移动中的主相意外。然而,对涉及的主要参数的参数研究表明包层搬迁动力学和所得的反应性效应对蒸汽摩擦因子和子组件的轴向功率分布非常敏感。因此,在ASTRID项目的框架中进一步研究了这些参数及其对瞬变的影响,以便在核心行为问题上巩固初步结论。

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