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The ultimate response guideline simulation and analysis by using TRACE for Lungmen ABWR nuclear power plant

机译:龙门ABWR核电站利用TRACE的最终响应准则模拟与分析

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摘要

In this research, the TRACE/SNAP model of Lungmen ABWR nuclear power plant (NPP) has been established for the simulation and analysis of ultimate response guideline (URG). The main actions of URG are depressurization and low pressure water injection of reactor and containment venting. This research focuses to assess the URG utility of Lungmen NPP under Fukushima-like conditions. This study consists of three steps. The first step is the establishment of Lungmen NPP TRACE/SNAP model. In order to evaluate the system response of TRACE/SNAP model, FSAR data (MSIV closure and loss of feedwater flow transient) were used to compare with the results of TRACE. The second step is the URG simulation and analysis under Fukushima-like conditions by using Lungmen NPP TRACE/SNAP model. In this step, the no URG case was also performed in order to evaluate the URG effectiveness of Lungmen NPP. In order to confirm the mechanical property and integrity of fuel rods, the final step is FRAPTRAN analysis. According to TRACE analysis results, the URG can keep the peak cladding temperature (PCT) below the criteria 1 088.7 K under Fukushima-like conditions which indicates that Lungmen NPP can be controlled in a safe situation. Nevertheless, if Lungmen NPP does not perform the URG under Fukushima-like conditions, the water level may drop lower than TAF after 1 100 s which means a safety issue about the fuel rods may be generated. The analysis results of FRAPTRAN also indicate the integrity of fuel rods cannot be kept under the above conditions.
机译:本研究建立了龙门ABWR核电厂(NPP)的TRACE / SNAP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福岛式条件下龙门核电厂的URG效用。这项研究包括三个步骤。第一步是建立龙门NPP TRACE / SNAP模型。为了评估TRACE / SNAP模型的系统响应,将FSAR数据(MSIV闭合和给水流量瞬态损失)与TRACE的结果进行了比较。第二步是使用龙门NPP TRACE / SNAP模型在类福岛条件下进行URG模拟和分析。在此步骤中,也未执行无URG案例以评估龙门NPP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TRACE分析结果,在类似福岛的情况下,URG可以使峰值包层温度(PCT)保持在1088.7 K以下,这表明在安全情况下可以控制龙门核电厂。但是,如果龙门核电厂在类似福岛的条件下未执行URG,则水位可能会在1100 s之后下降到低于TAF,这意味着可能会产生有关燃料棒的安全问题。 FRAPTRAN的分析结果还表明,在上述条件下无法保持燃料棒的完整性。

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  • 来源
    《Kerntechnik》 |2015年第3期|214-231|共18页
  • 作者单位

    Atom Energy Council, Inst Nucl Energy Res, Taoyuan 32546, Taiwan;

    Natl Tsing Hua Univ, Inst Nucl Engn & Sci, Hsinchu 30013, Taiwan;

    Natl Tsing Hua Univ, Inst Nucl Engn & Sci, Hsinchu 30013, Taiwan;

    Natl Tsing Hua Univ, Inst Nucl Engn & Sci, Hsinchu 30013, Taiwan;

    Natl Tsing Hua Univ, Inst Nucl Engn & Sci, Hsinchu 30013, Taiwan;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);
  • 原文格式 PDF
  • 正文语种 eng
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