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Assessment of GOTHIC and TRACE codes against selected PANDA experiments on a Passive Containment Condenser

机译:在无源安全壳冷凝器上针对选定的PANDA实验评估GOTHIC和TRACE代码

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摘要

Typical passive safety systems for ALWRs (Advanced Light Water Reactors) rely on the condensation of steam to remove the decay heat from the core or the containment. In the present paper the three-dimensional containment code GOTHIC and the one-dimensional system code TRACE are compared on the calculation of a variety of phenomena characterizing the response of a passive condenser submerged in a boiling pool. The investigation addresses the conditions of interest for the Passive Containment Cooling System (PCCS) proposed for the ESBWR (Economic Simplified Boiling Water Reactor). The analysis of selected separate effect tests carried out on a PCC (Passive Containment Condenser) unit in the PANDA large-scale thermal-hydraulic facility is presented to assess the code predictions. Both pure steam conditions (operating pressure of 3 bar, 6 bar and 9 bar) and the effect on the condensation heat transfer of non-condensable gases heavier than steam (air) and lighter than steam (helium) are considered. The role of the secondary side (pool side) heat transfer on the condenser performance is examined too. In general, this study shows that both the GOTHIC and TRACE codes are able to reasonably predict the heat transfer capability of the PCC as well as the influence of non-condensable gas on the system. A slight underestimation of the condenser performance is obtained with both codes. For those tests where the experimental and simulated efficiencies agree better the possibility of compensating errors among different parts of the heat transfer models is outlined. Besides, the pool side heat transfer coefficient is indicated to differ between GOTHIC and TRACE, revealing that the model implemented in TRACE might be more accurate. Finally, both codes deviate more from the experiments for the tests with helium, which is explained by the emerging of a complex circulatory flow pattern in the experiments that the models fail to predict.
机译:用于ALWR(先进轻水堆)的典型被动安全系统依靠蒸汽的冷凝来去除堆芯或密闭容器中的衰变热。在本文中,在计算表征浸没在沸腾池中的无源冷凝器的响应的各种现象的过程中,比较了三维安全壳代码GOTHIC和一维系统代码TRACE。该调查解决了为ESBWR(经济简化沸水反应堆)提议的被动安全壳冷却系统(PCCS)感兴趣的条件。提出了对在PANDA大型热工液压设施中的PCC(被动安全壳冷凝器)单元上进行的选定单独效果测试的分析,以评估代码预测。既要考虑纯蒸汽条件(工作压力为3 bar,6 bar和9 bar),也要考虑比蒸汽(空气)重和比蒸汽(氦气)轻的不可冷凝气体对冷凝热传递的影响。还检查了次级侧(池侧)传热对冷凝器性能的作用。总的来说,这项研究表明,GOTHIC和TRACE代码都能够合理地预测PCC的传热能力以及不可冷凝气体对系统的影响。使用这两个代码对冷凝器的性能略有低估。对于那些实验效率和模拟效率更好地吻合的测试,概述了在传热模型的不同部分之间补偿误差的可能性。此外,表明池侧传热系数在GOTHIC和TRACE之间有所不同,这表明在TRACE中实施的模型可能更准确。最后,两个代码与氦气测试的实验相差更大,这可以通过模型无法预测的实验中出现的复杂循环流模式来解释。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2014年第10期|542-557|共16页
  • 作者单位

    Nuclear Energy and Safety Research Department, Paul Scherrer Institut (PSI), 5232 Villigen PSI, Switzerland;

    Nuclear Energy and Safety Research Department, Paul Scherrer Institut (PSI), 5232 Villigen PSI, Switzerland;

    Nuclear Energy and Safety Research Department, Paul Scherrer Institut (PSI), 5232 Villigen PSI, Switzerland;

    Nuclear Energy and Safety Research Department, Paul Scherrer Institut (PSI), 5232 Villigen PSI, Switzerland;

  • 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
  • 关键词

  • 入库时间 2022-08-18 00:43:07

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