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Benchmarking LWR codes capability to model radionuclide deposition within SFR containments: An analysis of the Na ABCOVE tests

机译:标定LWR代码以模拟SFR密闭容器内放射性核素沉积的能力:Na ABCOVE测试分析

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摘要

Postulated BDBAs in SFRs might result in contaminated-coolant discharge at high temperature into the containment. A full scope safety analysis of this reactor type requires computation tools properly validated in all the related fields. Radionuclide transport, particularly within the containment, is one of those fields. This sets two major challenges: to have reliable codes available and to build up a sound data base. Development of SFR source term codes was abandoned in the 80's and few data are available at present. The ABCOVE experimental programme conducted in the 80's is still a reference in the field. Postulated BDBAs in SFRs might result in contaminated-coolant discharge at high temperature into the containment. A full scope safety analysis of this reactor type requires computation tools properly validated in all the related fields. Radionuclide deposition, particularly within the containment, is one of those fields. This sets two major challenges: to have reliable codes available and to build up a sound data base. Development of SFR source term codes was abandoned in the 80's and few data are available at present. The ABCOVE experimental programme conducted in the 80's is still a reference in the field. The present paper is aimed at assessing the current capability of LWR codes to model aerosol deposition within a SFR containment under BDBA conditions. Through a systematic application of the ASTEC, ECART and MELCOR codes to relevant ABCOVE tests, insights have been gained into drawbacks and capabilities of these computation tools. Hypotheses and approximations have been adopted so that differences in boundary conditions between LWR and SFR containments under BDBA can be accommodated to some extent. Two major outcomes result from this study: a reasonable approximation to the BDBA SFR scenario can be achieved with LWR codes if suitable hypotheses are made and development and implementation of new models is mandatory to enhance predictability to the required level in safety analyses. Vaporization, nucleation and oxidation of Na and turbulent agglomeration of particles are phenomena, for which models should be developed and implemented. Additionally, the importance of a good morphological characterization of aerosol particles has been highlighted.
机译:SFR中假定的BDBA可能导致高温下被污染的冷却液排入安全壳。这种反应堆类型的全面安全分析需要在所有相关领域中都经过正确验证的计算工具。放射性核素的运输,特别是在安全壳内的运输,就是其中之一。这提出了两个主要挑战:要有可靠的代码并建立健全的数据库。 SFR源术语代码的开发在80年代被放弃,目前尚无可用数据。在80年代进行的ABCOVE实验程序仍然是该领域的参考。 SFR中假定的BDBA可能导致高温下被污染的冷却液排入安全壳。这种反应堆类型的全面安全分析需要在所有相关领域中都经过正确验证的计算工具。放射性核素沉积,特别是在安全壳内,是这些领域之一。这提出了两个主要挑战:要有可靠的代码并建立健全的数据库。 SFR源术语代码的开发在80年代被放弃,目前尚无可用数据。在80年代进行的ABCOVE实验程序仍然是该领域的参考。本文旨在评估LWR代码在BDBA条件下对SFR密闭空间内的气溶胶沉积进行建模的能力。通过将ASTEC,ECART和MELCOR代码系统地应用到相关的ABCOVE测试中,已经洞悉了这些计算工具的缺点和功能。已采用假设和近似值,以便可以在一定程度上适应BDBA下LWR和SFR围护结构之间边界条件的差异。这项研究得出两个主要结果:如果做出了适当的假设,并且可以开发和实施新模型以将安全性分析中的可预测性提高到所需水平,则可以使用LWR代码对BDBA SFR场景进行合理近似。 Na的汽化,成核和氧化以及颗粒的湍流团聚是现象,应为此开发和实施模型。另外,已经强调了气溶胶颗粒的良好形态表征的重要性。

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  • 来源
    《Nuclear Engineering and Design》 |2013年第12期|772-784|共13页
  • 作者单位

    CIEMAT, Unit of Nuclear Safely Research, Av. Complutense, 40,28040 Madrid, Spain;

    CIEMAT, Unit of Nuclear Safely Research, Av. Complutense, 40,28040 Madrid, Spain;

    Nuclear and Industrial Plant Safety Team, Power Generation System Department, RSE, via Rubattino 54,20134 Milano, Italy;

  • 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
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