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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 Ⅲ. Verification against representative transient tests
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Advanced treatment of zircaloy cladding high-temperature oxidation in severe accident code calculations Part Ⅲ. Verification against representative transient tests

机译:严重事故代码计算中锆合金熔覆层高温氧化的深度处理第三部分。针对代表性瞬态测试的验证

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摘要

The treatment of zirconium oxidation kinetics in severe accident (SA) codes has been the subject of many discussions and controversies in recent years. The main problem was the existence of several correlations which could lead to large differences in the calculated results. It appeared clearly that there was a need to converge towards a common understanding of the physical processes that must be modeled (oxygen diffusion, blanketing effect, etc.) and an agreed database among code developers and users. It would help reducing an important source of uncertainties in SA calculations. The kinetic correlation database, obtained as a result of examination of complementary experimental data in Parts I and II, is applied here to analyze a few high-temperature separate-effects tests and bundle experiments where Zry oxidation reaction played a dominant role. The 1C ARE/C ATHARE computer code developed by IRSN is used to check the validity of the high-temperature correlations derived in Parts Ⅰ and Ⅱ. The physical modeling provided by the code includes detailed account of specific features of chemical interactions between fuel rod cladding and steam. In particular, high reaction rates at T > 2000 K are moderated by two effects, examined in Part Ⅰ: steam blanketing during thin oxide layers growth and transition to oxidation of α-Zr(O) phase after total consumption of primary β-Zr in cladding metallic part. When applied to separate-effects tests, the evaluated parabolic correlations have shown their applicability to different types of temperature transients taking into account Zry oxidation specifics in rod geometry. The bundle integral experiments QUENCH-06 and PHEBUS B9+ did not lead to extremely large temperature excursions. Calculated temperatures, hydrogen production and oxide thickness, as well as parameters of melt relocation were found to agree well with experimentally measured values. As a result of this study, we believe that the new best-fitted correlations, obtained in agreement with available experimental data, can be used in further studies and can improve predictive power of the codes. The continuation of the current work will be the application of ICARE/CATHARE code with best-fitted Zry oxidation correlations to NPP accident scenarios.
机译:近年来,严重事故(SA)代码中锆氧化动力学的处理已成为许多讨论和争议的主题。主要问题是存在几种相关性,这些相关性可能导致计算结果出现较大差异。显然,有必要对必须建模的物理过程(氧气扩散,覆盖效应等)和代码开发人员和用户之间达成一致的数据库达成共识。这将有助于减少SA计算中不确定性的重要来源。通过检查第I部分和第II部分中的补充实验数据获得的动力学相关性数据库在这里用于分析一些高温单独效应试验和Zry氧化反应起主要作用的束实验。用IRSN开发的1C ARE / C ATHARE计算机代码检查第一和第二部分中得出的高温相关性的有效性。代码提供的物理模型包括燃料棒包壳与蒸汽之间化学相互作用的特定特征的详细说明。尤其是,在T> 2000 K时的高反应速率受到两个影响的缓解,这在第一部分中进行了研究:薄氧化层生长期间的蒸汽覆盖和在完全消耗初级β-Zr之后转变为α-Zr(O)相的氧化。覆层金属零件。当应用于分离效应测试时,考虑到杆几何中的Zry氧化特性,所评估的抛物线相关性已显示出它们对不同类型的温度瞬变的适用性。束积分实验QUENCH-06和PHEBUS B9 +不会导致很大的温度偏移。发现计算的温度,产氢量和氧化物厚度以及熔体迁移参数与实验测量值非常吻合。这项研究的结果是,我们认为,与现有实验数据一致获得的新的最佳拟合相关性可以用于进一步的研究中,并且可以提高代码的预测能力。当前工作的继续将是将具有最适合Zry氧化相关性的ICARE / CATHARE代码应用于NPP事故场景。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2004年第1期|p.97-109|共13页
  • 作者单位

    Institut de Radioprotection et de Surete Nucleaire (IRSN), Division of Major Accidents Prevention, BP 3, 13 115 St Paul lez Durance, France;

  • 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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