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In-containment source term predictability of ASTEC-Na: Major insights from data-predictions benchmarking

机译:ASTEC-Na的容器内源术语可预测性:数据预测基准测试的主要见解

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摘要

Modeling the containment response to a sodium pool fire is to be one of the key aspects of any comprehensive safety evaluation of the new generation of sodium cooled fast reactors. Through a peer review of earlier experimental investigations some useful data can be collected and then used for assessing the current analytical capabilities to model severe accidents or some of their specific aspects. This paper provides major insights into the in-containment aerosol behavior predictability of ASTEC-Na (CPA* module) during Na-pool fires. By comparing against tests from the ABCOVE (AB1 and AB2) and FAUNA (F2) programs, it has been shown that experimental trends can be roughly reproduced with a singlecell approach whenever natural convection is effective in making the vessel atmosphere uniform both thermally and in composition. Nonetheless, the present heavy parametrization of ASTEC-Na models should be avoided or strongly supported by further experimentation that allows setting sound default values, concerning both combustion energy distribution and aerosol formation and distribution. Anyway, the peer data review has highlighted that a meaningful comparison to predictions is not always feasible due to large data uncertainties, particularly at the beginning of Na burning. As for the particle ageing, the comparisons set seems to indicate that transformation from oxides to hydroxides is predicted to be too slow; nevertheless, a more extensive benchmarking should be conducted to confirm it. (C) 2017 Elsevier B.V. All rights reserved.
机译:对钠池火的安全壳响应进行建模,将成为新一代钠冷却快堆任何全面安全评估的关键方面之一。通过对早期实验研究的同行评审,可以收集一些有用的数据,然后将其用于评估对严重事故或其某些方面进行建模的当前分析能力。本文提供了有关在Na-pool火灾期间ASTEC-Na(CPA *模块)的气溶胶行为可预测性的主要见解。通过与ABCOVE(AB1和AB2)和FAUNA(F2)程序的测试进行比较,结果表明,只要自然对流有效地使容器内的空气在热和成分上均一,则单细胞方法可以大致再现实验趋势。 。尽管如此,应该通过允许设置合理的默认值(涉及燃烧能量分布以及气溶胶形成和分布)的进一步实验来避免或强烈支持ASTEC-Na模型目前繁重的参数化。无论如何,同行数据审查都强调指出,由于大的数据不确定性,尤其是在Na燃烧开始时,与预测进行有意义的比较并不总是可行的。至于颗粒老化,比较结果似乎表明从氧化物到氢氧化物的转变预计太慢。但是,应该进行更广泛的基准测试以确认这一点。 (C)2017 Elsevier B.V.保留所有权利。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2017年第8期|269-281|共13页
  • 作者单位

    CIEMAT, Unit Nucl Safety Res, Av Complutense 40, E-28040 Madrid, Spain;

    CIEMAT, Unit Nucl Safety Res, Av Complutense 40, E-28040 Madrid, Spain;

    IRSN, Nucl Safety Div, St Paul Les Durance, France;

    Italian Natl Agcy New Technol Energy & Sustainabl, Bologna, Italy;

    Gesell Anlagen & Reaktorsicherheit GRS gGmbH, Cologne, Germany;

  • 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

    ASTEC-Na code; SFR containment benchmark; Sodium pool fire; Source term;

    机译:ASTEC-Na代码;SFR控制基准;钠池火;源术语;
  • 入库时间 2022-08-18 00:41:24

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