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首页> 外文期刊>Nuclear Engineering and Design >Advanced treatment of zircaloy cladding high-temperature oxidation in severe accident code calculations Part Ⅰ. Experimental database and basic modeling
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Advanced treatment of zircaloy cladding high-temperature oxidation in severe accident code calculations Part Ⅰ. Experimental database and basic modeling

机译:严重事故代码计算中锆合金熔覆层高温氧化的高级处理(第一部分)。实验数据库和基本建模

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摘要

Progress in the treatment of zirconium oxidation kinetics in different severe accident (SA) codes and convergence towards an agreed data base are required for the reliable verification of sophisticated LWR core degradation models. Focused on the comprehensive experimental studies the available information on the high-temperature oxidation kinetics of zircaloy (Zry) is evaluated. Important discrepancies between results for the high-temperature range are interpreted in terms of different experimental and evaluation procedures. The critical assessment identifies the following items, which require separate consideration in the simplified convention of using fixed reaction rate correlations for the high and low temperature ranges: the co-existence of two oxide phase sub-layers gives rise to a transitional kinetic response in an intermediate temperature range. Towards higher temperatures the validity of the correlations approach (assuming reaction rate control as in a semi-infinite solid-state diffusion system) is restricted further, on the one hand by kinetic control within the gas phase (initial oxidation range), on the other hand by metal matrix consumption (final oxidation range). The analytical treatment of the two last-mentioned concomitant phenomena is given, and the consideration allows to reconcile apparent discrepancies between experimental results. A reasonable base of combined data is thus identified, for a moment with certain uncertainty, which is not suitable for direct application. In Part Ⅱ, the kinetic base will be further verified and refined by statistical evaluation of complementary experimental data and transferred to the form, allowing implementation in codes. In Part Ⅲ, the satisfactory application in ICARE2 code calculations of separate-effect and bundle experiments will be presented.
机译:为了可靠地验证复杂的轻水堆堆芯退化模型,需要以不同的严重事故(SA)密码处理锆氧化动力学并取得共识,以达到共识的数据库。侧重于全面的实验研究,评估了锆合金(Zry)高温氧化动力学的可用信息。根据不同的实验和评估程序,可以解释高温范围内结果之间的重要差异。关键评估确定以下项目,在高温和低温范围内使用固定的反应速率相关性的简化约定中,需要单独考虑以下事项:两个氧化物相子层的共存会引起在反应过程中的过渡动力学响应。中间温度范围。对于更高的温度,一方面通过气相(初始氧化范围)内的动力学控制,进一步限制了相关方法(假设在半无限固态扩散系统中进行反应速率控制)的有效性。手工消耗的金属基质(最终氧化范围)。给出了对最后两个同时出现的现象的分析处理,该考虑因素可以调和实验结果之间的明显差异。因此,确定了组合数据的合理基础,但存在一定的不确定性,这不适合直接应用。在第二部分中,将通过对补充实验数据进行统计评估来进一步验证和完善动力学基础,并将其转化为形式,从而可以用代码实现。在第三部分中,将给出令人满意的在单独效果和捆绑实验的ICARE2代码计算中的应用。

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  • 来源
    《Nuclear Engineering and Design》 |2004年第1期|p.75-84|共10页
  • 作者单位

    Forschungszentrum Karlsruhe GmbH, Institut fuer Materialforschung (FZK, IMF Ⅲ), Karlsruhe, 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 原子能技术;
  • 关键词

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