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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 Ⅱ. Best-fitted parabolic correlations
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Advanced treatment of zircaloy cladding high-temperature oxidation in severe accident code calculations PART Ⅱ. Best-fitted parabolic correlations

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二部分。最拟合的抛物线相关

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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. The kinetic data base, to be defined for recommended application in severe accident codes, developed by critical assessment of the essential experimental results in Part Ⅰ, is further verified and refined. The experiments of Prater and Courtright, the main high temperature data source, require re-evaluation to account for the temperature gradients across the test specimens. This task is performed by Pawel' model extension for treatment of temperature gradients within scales and development of the solution algorithm. Statistical evaluation of the original data within reasonable parameter limits allows to deduce corrected rate coefficients for the corresponding isothermal case. Moreover, the co-existence of two oxide phase sub-layers, giving rise to a transitional kinetic response in an intermediate temperature range, is treated by model extension and described in terms of an "effective" diffusivity; a smooth transition to the high temperature range is obtained. In total, the deduced kinetics with certain reduction in reaction rate at high temperatures, compared to original evaluation of Prater and Courtright, is able to verify the combined original experimental results. At the same time contradictory trends are explained and reconciled on basis of the specific experimental procedures and constraints. The examination results support the conviction that the presented correlations are adequate transfer functions for the direct application in codes. Their use can be recommended for every code, apt for the correlations approach. In Part Ⅲ the verification of obtained correlations in frames of ICARE/CATHARE code against 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。进一步验证和完善了通过严格评估第一部分中的基本实验结果而建立的动力学数据库,以供建议用于严重事故代码中。主要高温数据源Prater和Courtright的实验需要重新评估,以说明整个试样的温度梯度。通过Pawel的模型扩展来执行此任务,以处理标度内的温度梯度并开发求解算法。在合理的参数范围内对原始数据进行统计评估,可以推导出相应等温情况下的校正速率系数。此外,两个氧化物相亚层的共存会在中间温度范围内引起过渡动力学响应,通过模型扩展进行处理并以“有效”扩散率进行描述。获得了向高温范围的平稳过渡。总的来说,与Prater和Courtright的原始评估结果相比,在高温下反应速率有所降低的推论动力学能够验证合并后的原始实验结果。同时,根据具体的实验程序和约束条件对矛盾趋势进行了说明和调和。检查结果支持这样的信念,即所提出的相关性对于直接在代码中应用是足够的传递函数。可以为每个代码推荐它们的使用,以适合于相关方法。在第三部分中,将对在ICARE / CATHARE代码的帧中获得的相关性进行验证,以证明它们是分别作用和捆绑实验的。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2004年第1期|p.85-96|共12页
  • 作者单位

    Nuclear Safety Institute of Russian Research Center "Kurchatov Institute ", (NSI RRC KI), Moscow, 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 原子能技术;
  • 关键词

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