Comparison of correlations for thermal creep of FBR MOX

IF 3.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Progress in Nuclear Energy Pub Date : 2024-11-08 DOI:10.1016/j.pnucene.2024.105516

Rolando Calabrese , Shun Hirooka

引用次数: 0

Abstract

Thermal creep is one of the key properties of mixed oxide (MOX) fuel for innovative fast reactors. Thermal creep of fuel affects markedly the interaction between the fuel and the cladding. A review of correlations available in the literature is presented. The effect of porosity, plutonium concentration, and stoichiometry are discussed also in the light of recent numerical results. Our analysis pointed out some inconsistencies concerning the modelling of the effect of porosity on diffusional creep and a re-evaluation of the effect of plutonium concentration. The discussion suggested that Evans's findings on the effect of stoichiometry should be better assessed as well as the level of increase in creep moving towards stoichiometry. Typical operating conditions of fast breeder reactors (FBRs) confirmed the need for an extension of porosity and temperature correlations' domains. Besides this, a new correlation based on a separate-effect approach has been proposed for fuel performance codes.

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FBR MOX 热蠕变相关性比较

热蠕变是用于创新快堆的混合氧化物（MOX）燃料的关键特性之一。燃料的热蠕变会明显影响燃料与包壳之间的相互作用。本文对文献中的相关性进行了综述。还根据最新的数值结果讨论了孔隙率、钚浓度和化学计量的影响。我们的分析指出了在模拟孔隙率对扩散蠕变的影响和重新评估钚浓度的影响方面存在的一些不一致之处。讨论表明，应更好地评估埃文斯关于化学计量影响的研究结果，以及向化学计量发展时蠕变增加的程度。快中子增殖反应堆（FBRs）的典型运行条件证实了扩展孔隙率和温度相关性领域的必要性。此外，还为燃料性能代码提出了一种基于分离效应方法的新相关性。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

Progress in Nuclear Energy 工程技术-核科学技术

CiteScore

5.30

自引率

14.80%

发文量

331

审稿时长

3.5 months

期刊介绍： Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.