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首页> 外文期刊>Annals of nuclear energy >Estimation of the fuel debris thermal energy at the time of the major core slumping of Fukushima Daiichi Nuclear Power Plant Unit-3 with MELCOR-2.2
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Estimation of the fuel debris thermal energy at the time of the major core slumping of Fukushima Daiichi Nuclear Power Plant Unit-3 with MELCOR-2.2

机译：熔融-2.2福岛核电站核电厂核电厂核电厂核心滞后时燃料碎片热能估算

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To provide supportive information to understand the current debris status in Fukushima Daiichi Nuclear Power Plant Unit-3, sensitivity analyses have been carried out with MELCOR-2.2 for two scenarios, with/without direct leakage from the Reactor Pressure Vessel (RPV) to the Drywell (D/W). The particular focus of the analyses is the estimated debris thermal energy up to and at the time of the major core slumping event, which may be the key to determine the following debris cooling and failure mechanism of the lower head of the RPV. In the analysis, the debris relocation velocity from the core region to the RPV lower head (VFALL), the number of Safety Relief Valves (SRVs) opening, and the amount of core slumping at the major RPV pressure peak were tuned so that the plant data of RPV and PCV pressure from ca. 9:00 to 12:00 March 13th 2011could be reproduced in each scenario. Best-estimate case conditions are summarized for the with/without direct leakage from RPV to D/W scenarios. As a result, as a consideration common to both scenarios, MELCOR analysis tends to estimate significant core oxidation before Automatic Depressurization System (ADS) actuation, and concomitantly estimates little core oxidation from the time after ADS to the time of the major RPV pressure peak. In addition, although a remarkable difference was found in the amount of hydrogen generated in RPV during the major core slumping between the best-estimate with/without leakage cases, limited difference can be observed for the core oxidation heat generation during the major core slumping. This is because the early Zircaloy oxidation prior to ADS actuation in the current MELCOR modelling resulted that the hydrogen generation source during the major core slumping at 12:00 March 13th was primarily from oxidation of stainless steel, which was not as exothermic as that of Zr oxidation. (C) 2021 Elsevier Ltd. All rights reserved.
机译：为了提供支持的信息，了解福岛核电站核电厂单元-3中的当前碎片状态，已经使用熔体-2.2进行了敏感性分析，两种情况进行了两种情况，与反应器压力容器（RPV）直接泄漏到干燥（d / w）。分析的特殊焦点是主要核心坍塌事件的估计碎片热能，其可以是确定RPV下部头部的以下碎屑冷却和失效机制的关键。在分析中，从核心区域到RPV下部头部（VFL）的碎片重定位速度，安全释放阀（SRV）开口的数量以及主要RPV压力峰处的核心坍塌的数量使得植物来自CA的RPV和PCV压力的数据。 2011年3月13日上午9点到12点到12:00在每种情况下都被复制。最佳估计案例条件总结了来自RPV至D / W场景的带/不直接泄漏。结果，作为两种情景共同的考虑，熔体分析倾向于在自动减压系统（ADS）致动之前估计显着的核心氧化，并伴随着广告后的时间估计到主要RPV压力峰的时间之后的少量核心氧化。此外，尽管在RPV中产生的氢气量的主要核心在最佳估计与/无泄漏案件之间的主要核心期间发现了显着差异，但是对于在主要核心坍塌期间，可以观察到有限差异用于核心氧化热产生。这是因为在目前熔体建模中致动之前的早期锆铝氧化导致氢气产生源在3月13日12:00的主要核心坍塌，主要来自不锈钢的氧化，这与Zr的不锈钢不那么放热氧化。 （c）2021 elestvier有限公司保留所有权利。

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