开发用于 LVR-15 严重事故评估的 MELCOR 模型

Energies Pub Date : 2024-07-10 DOI:10.3390/en17143384
Alain Flores y Flores, G. Mazzini, A. Dambrosio
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引用次数: 0

摘要

LVR-15 是一个轻水槽式研究反应堆,位于布拉格附近的雷兹研究中心(CVR),反应堆安装在屏蔽罩下的不锈钢容器中。该反应堆在大气压力下的稳态功率可达 10 兆瓦,并通过强制循环进行冷却。2011 年,燃料从高浓铀(HEU)更换为低浓铀(LEU)。2017 年后,国家核安全局(SUJB)要求 CVR 在设计扩展条件 B(DEC-B)下对 LVR-15 进行评估。为此,在 MELCOR 代码中开发了一个新模型,该模型可模拟轻水核电站严重事故(SA)的进展情况,并估计反应堆在 SA 条件下的行为。该模型是通过收集 LVR-15 的相关信息建立的。由于研究堆可根据堆芯部件的位置采用不同的堆芯构型,因此选择了燃料最多的堆芯构型(最热活动 K221)。然后,为了创建径向节点化,我们获得了堆芯部件的详细信息,并将其分为 5 个径向环和 27 个轴向层。模拟运行时使用了从 K221 试验中收集的边界条件,并将结果与该试验的参考值进行了比较,误差率可忽略不计。冷却剂入口和出口温度的参考值分别为 318.18 K 和 323.5 K,而在模拟中,入口温度的稳定状态达到 319 K,出口温度达到 324 K。此外,最热组件的包层温度与参考值(353.72 K)和稳态模拟结果(362 K)进行了比较。在今后的工作中,将模拟导致严重事故的不同瞬态。在使用 MELCOR 模拟 LVR-15 反应堆时,需要特别注意铝包层燃料组件,因为该模型需要一些假设来应对现象学限制。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Development of a MELCOR Model for LVR-15 Severe Accidents Assessment
LVR-15 is a light-water-tank-type research reactor placed in a stainless-steel vessel under a shielding cover located in the Research Centre Rez (CVR) near Prague. It is operated at a steady-state power of up to 10 MWt under atmospheric pressure and is cooled by forced circulation. In 2011, the fuel was replaced, going from high-enriched uranium (HEU) to low-enriched uranium (LEU). After 2017, the State Office for Nuclear Safety (SUJB) asked CVR to evaluate the LVR-15 under Design Extended Conditions B (DEC-B). For this reason, a new model was developed in the MELCOR code, which allows for modelling the progression of a severe accident (SA) in light-water nuclear power plants and estimating the behaviour of the reactor under SA conditions. The model was built by collecting information about the LVR-15. Since the research reactor can have different core configurations according to the location of the core components, the core configuration with the most fuel (hottest campaign K221) was selected. Then, to create the radial nodalisation, the details of the core components were obtained and grouped in five radial rings and 27 axial levels. The simulation was run with the boundary conditions collected from campaign K221, and the results were compared with the reference values of the campaign with a negligible percentage of error. For the coolant inlet and outlet temperature, the reference values were 318.18 K and 323.5 K, respectively, while for the simulation, the steady state reached 319 K for the inlet temperature and 324 K for the outlet temperature. Additionally, the cladding temperature of the hottest assembly was compared with the reference value (353.72 K) and the steady-state simulation results (362 K). In future work, different transients leading to severe accidents will be simulated. When simulating the LVR-15 reactor with MELCOR, specific attention is required for the aluminium-cladded fuel assemblies, as the model requires some assumptions to cope with the phenomenological limitations.
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