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Development of the fuel assembly pin-by-pin model in the KORSAR/GP code

机译:用KORSAR / GP代码开发燃料组件销接销模型

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摘要

This paper presents the pin-by-pin thermal-hydraulic model of the fuel assembly (FA) developed with the KORSAR/GP code. Its application for simulation of separate fuel rods in the FA is demonstrated.Usually the safety margins are calculated using a "hot channel" model for NPP (Nuclear Power Plant) safety analysis. This approach is conservative. The pin-by-pin simulation provides more realistic results and wider safety margins.The new KORSAR/GP pin-by-pin model was cross-validated with the TIGR-SP code which is used by OKB "GIDROPRESS" for FA steady-state operation assessment. DNBR (departure from nucleate boiling ratio) difference between KORSAR/GP and TIGR-SP does not exceed 3%. Thus, the KORSAR/GP pin-by-pin model provides correct results.The nodalization of the developed model consists of parallel 1D hydraulic elements (channels). The cells of these channels are connected to each other by special elements - cross junctions and turbulent mixing elements (CJ and TM). The paper also deals with the investigation of influence of these elements on DNBR calculation.
机译:本文介绍了使用KORSAR / GP代码开发的燃料组件(FA)的逐针热工液压模型。演示了其在FA中模拟单独燃料棒的应用。通常,使用“热通道”模型进行NPP(核电厂)安全分析来计算安全裕度。这种方法是保守的。逐引脚仿真提供了更逼真的结果和更大的安全裕度。新的KORSAR / GP逐引脚模型与TIGR-SP代码进行了交叉验证,OKB“ GIDROPRESS”将其用于FA稳态操作评估。 KORSAR / GP和TIGR-SP之间的DNBR(偏离核沸腾率)的差异不超过3%。因此,KORSAR / GP逐针模型提供了正确的结果。开发模型的节点化包含平行的一维液压元件(通道)。这些通道的单元通过特殊元素-交叉结和湍流混合元素(CJ和TM)相互连接。本文还研究了这些元素对DNBR计算的影响。

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  • 来源
    《Nuclear Engineering and Design》 |2019年第12期|110203.1-110203.9|共9页
  • 作者单位

    JSC Expt & Design Org GIDROPRESS Podolsk Russia;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
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