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首页> 外文期刊>Annals of nuclear energy >The ultimate response guideline simulation and analysis using TRACE, MAAP5, and FRAPTRAN for the Chinshan Nuclear Power Plant
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The ultimate response guideline simulation and analysis using TRACE, MAAP5, and FRAPTRAN for the Chinshan Nuclear Power Plant

机译:金山核电站使用TRACE,MAAP5和FRAPTRAN的最终响应准则仿真和分析

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摘要

In this research, the TRACE and MAAP5 model of Chinshan BWR/4 nuclear power plant (NPP) has been established for the simulation and analysis of ultimate response guideline (URG). The main actions of URG are the depressurization and low pressure water injection of the reactor and containment venting. This research focuses to assess the usefulness of the URG under Fukushima-like conditions. This study consists of three steps. The first step is the establishment of Chinshan NPP TRACE and MAAP5 model. The second step is the URG simulation and analysis under Fukushima-like conditions by using Chinshan NPP TRACE and MAAP5 model. In this step, the base case without URG case was also performed in order to evaluate the URG effectiveness of Chinshan NPP. In order to confirm the mechanical property and integrity of fuel rods, the final step is FRAPTRAN analysis. According to TRACE and MAAP5 analysis results under Fukushima-like conditions, the URG can keep the peak cladding temperature (PCT) below the criteria 1088.7 K. It indicates that Chinshan NPP can be controlled in a safe situation. If under Fukushima-like conditions Chinshan NPP does not perform the URG, the water level may drop below the TAF (top of active fuel) which means a fuel melt safety issue may exist. (C) 2017 Elsevier Ltd. All rights reserved.
机译:在本研究中,建立了金山BWR / 4核电厂(NPP)的TRACE和MAAP5模型,用于最终响应准则(URG)的仿真和分析。 URG的主要作用是反应堆的减压和低压注水以及安全壳排气。这项研究的重点是评估在类似福岛的条件下URG的有效性。这项研究包括三个步骤。第一步是建立金山NPP TRACE和MAAP5模型。第二步是使用金山NPP TRACE和MAAP5模型在类福岛条件下进行URG模拟和分析。在此步骤中,还执行了没有URG案例的基本案例,以评估金山核电厂的URG有效性。为了确认燃料棒的机械性能和完整性,最后一步是FRAPTRAN分析。根据在类似福岛条件下的TRACE和MAAP5分析结果,URG可以使峰值包层温度(PCT)保持在1088.7 K以下。这表明,金山核电厂可以在安全的情况下得到控制。如果在类似福岛的条件下,金山核电厂没有执行URG,则水位可能会下降到TAF(活性燃料顶部)以下,这意味着可能存在燃料熔体安全问题。 (C)2017 Elsevier Ltd.保留所有权利。

著录项

  • 来源
    《Annals of nuclear energy 》 |2017年第5期| 402-411| 共10页
  • 作者单位

    ROC, Inst Nucl Energy Res Atom Energy Council, 1000,Wenhua Rd, Longtan Township 32546, Taoyuan County, Taiwan;

    Natl Tsing Hua Univ, Inst Nucl Engn & Sci, Nucl & New Energy Educ & Res Fdn, 101,Sect 2,Kuang Fu Rd, Hsinchu 30013, Taiwan;

    ROC, Inst Nucl Energy Res Atom Energy Council, 1000,Wenhua Rd, Longtan Township 32546, Taoyuan County, Taiwan;

    Natl Tsing Hua Univ, Inst Nucl Engn & Sci, Nucl & New Energy Educ & Res Fdn, 101,Sect 2,Kuang Fu Rd, Hsinchu 30013, Taiwan;

    Natl Tsing Hua Univ, Inst Nucl Engn & Sci, Nucl & New Energy Educ & Res Fdn, 101,Sect 2,Kuang Fu Rd, Hsinchu 30013, Taiwan;

    Natl Tsing Hua Univ, Inst Nucl Engn & Sci, Nucl & New Energy Educ & Res Fdn, 101,Sect 2,Kuang Fu Rd, Hsinchu 30013, Taiwan;

    Taiwan Power Co, Dept Nucl Safety, 242,Sect 3,Roosevelt Rd, Taipei, Taiwan;

    Taiwan Power Co, Dept Nucl Safety, 242,Sect 3,Roosevelt Rd, Taipei, Taiwan;

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  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    TRACE; MAAP5; FRAPTRAN; BWR; Safety analysis;

    机译:痕迹;MAAP5;FRAPTRAN;BWR;安全性分析;

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