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首页> 外文期刊>Annals of nuclear energy >Thermal analysis of ceramic nuclear fuels for the HPLWR
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Thermal analysis of ceramic nuclear fuels for the HPLWR

机译：HPLWR陶瓷核燃料的热分析

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摘要

The High Performance Light Water Reactor (HPLWR) is one of the most promising designs of the Super-Critical Water Reactor (SCWR). The use of uranium nitride (UN) and uranium carbide (UC), as alternative nuclear fuels for the SCWR, offer the advantage of high thermal conductivity compared to uranium dioxide (UO2). For the analysis of these alternative nuclear fuels in SCWRs, some important design features must be considered. One of them is the porosity; the nuclear fuel is manufactured with different porosity values, as high as 20%, to reduce its hardness and swelling, influencing its thermal conductivity. Another issue is related to the chemical reactivity of UN and UC with water and nickel, which forces the use of coatings for fuel pellets. In this paper, a preliminary thermal-hydraulic analysis, using CFD codes, of the HPLWR fuel assembly, focused on the thermal behavior of ceramic fuel, was carried out. The use of UN coated with zirconium carbide layers and UC coated with titanium nitride layers were analyzed. The impact of porosity induced changes in fuel temperature profiles was analyzed. The radial and axial fuel temperature distributions were obtained for all cases. It was found that the maximum temperature values obtained using UN and UC, both coated and uncoated, were lower than those obtained with UO2. It was found that the porosity changes on the proposed fuels have a small influence on the maximum fuel temperature. (C) 2018 Elsevier Ltd. All rights reserved.
机译：高性能轻水反应堆（HPLWR）是超临界水反应堆（SCWR）最有前途的设计之一。与二氧化铀（UO2）相比，使用氮化铀（UN）和碳化铀（UC）作为SCWR的替代核燃料具有优势。为了分析短波堆中的这些替代核燃料，必须考虑一些重要的设计特征。其中之一是孔隙率。核燃料以不同的孔隙率值（高达20％）制造，以降低其硬度和溶胀度，从而影响其热导率。另一个问题与UN和UC与水和镍的化学反应有关，这迫使使用燃料颗粒涂层。在本文中，使用CFD代码对HPLWR燃料组件进行了初步的热工液压分析，重点是陶瓷燃料的热行为。分析了涂有碳化锆层的UN和涂有氮化钛层的UC的使用。分析了孔隙率引起的燃料温度曲线变化的影响。获得了所有情况下的径向和轴向燃料温度分布。发现使用UN和UC涂覆和未涂覆的最高温度值均低于使用UO2获得的最高温度值。发现所提出的燃料的孔隙率变化对最高燃料温度的影响很小。 （C）2018 Elsevier Ltd.保留所有权利。

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  • 来源
    《Annals of nuclear energy》 |2019年第5期|227-236|共10页
  • 作者

    Castro Landy; Delgado Genrry; Garcia Carlos; Dominguez Dany S.;

  • 作者单位

    Univ Nacl Autonoma Mexico, Posgrad Ingn, Ciudad Univ, Mexico City 04510, DF, Mexico;

    Inst Super Tecnol & Ciencias Aplicadas, Ave Salvador Allende, Havana 10700, Cuba;

    Inst Super Tecnol & Ciencias Aplicadas, Ave Salvador Allende, Havana 10700, Cuba;

    Univ Estadual Santa Cruz, Programa Posgrad Modelagem Computac, Rodovia Jorge Amado,Km 16, BR-45662900 Ilheus, BA, Brazil|Univ Politecn Valencia, Camino Vera 14, E-46022 Valencia, Spain;

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  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    HPLWR; SCWR; Ceramic fuel; Uranium carbide; Uranium nitride; Coated nuclear fuel;

    机译：HPLWR;SCWR;陶瓷燃料;碳化铀;氮化铀;涂层核燃料;

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