首页> 外文期刊>Nuclear Technology >COUPLING OF A LUMPED PARAMETER AND A FINITE DIFFERENCE MODEL FOR ESTIMATION OF A REACTIVITY- INDUCED TRANSIENT IN A PWR WITH ANNULAR FUEL RODS
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COUPLING OF A LUMPED PARAMETER AND A FINITE DIFFERENCE MODEL FOR ESTIMATION OF A REACTIVITY- INDUCED TRANSIENT IN A PWR WITH ANNULAR FUEL RODS

机译:集总参数和有限差分模型的耦合,用于估算带环形燃料棒的压水堆的反应性瞬态

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摘要

This paper develops a finite difference and a semianalytical model to evaluate the thermal behavior of fuel rods during a hypothetical reactivity-induced transient (absorber rod ejection) in a pressurized water reactor (PWR). The calculations are carried out for two different reactor core designs, namely, for a typical PWR core with typical fuel rods and for a modified PWR core containing annular fuel rods. The overall dimensions of the core internals and fuel assemblies are unchanged, and the total number of fuel assemblies is the same in both designs. The finite difference code was verified on the results provided by the semianalytical model. In the calculations, two point models were used (neutron kinetics to compute the fission power of the reactor; power balance of coolant in the active core region). The point models were coupled to the one-dimensional, finite difference heat conductivity model to calculate the radial temperature profile in the solid and the annular cylindrical pellets (UO_2). The latter are the constituent part of annular fuel rods cooled both on their external and internal surfaces. The fuel, cladding, and fluid temperatures were evaluated for the annular and the solid fuel design in the hot spot, where the maximum allowable power rating of rods is 2.5 times higher than the average one. It was assumed that before the transient, (a) the reactor with annular fuel runs continuously at higher nominal power (150%) and at higher nominal coolant flow rate (150%) at the core inlet than the reference reactor with solid fuel (100%) and (b) the modified and the reference reactors have the same coolant temperature at the core inlet and the same temperature rise of coolant along their core. These conditions correspond to a 150% power uprate of the reference reactor. The coupled models require limited computational resources only. The calculated results showed that during the transient, in the annular fuel pellet, the temperatures peaked at considerably lower values, even at 150% power, than in the solid pellets at 100% power. These evaluations show that in the case of the reactivity-induced transient analyzed, the annular fuel cooled from both sides has a better safety performance than the solid fuel cooled only on its external surface.
机译:本文建立了一个有限差分和一个半分析模型,以评估在压水反应堆(PWR)中假设反应性诱发的瞬变(吸收棒排出)期间燃料棒的热行为。计算是针对两种不同的反应堆堆芯设计进行的,即针对具有典型燃料棒的典型PWR堆芯和包含环形燃料棒的改进型PWR堆芯。堆芯内部组件和燃料组件的总体尺寸没有变化,两种设计中燃料组件的总数相同。根据半解析模型提供的结果验证了有限差分代码。在计算中,使用了两点模型(中子动力学来计算反应堆的裂变功率;有效堆芯区域中冷却剂的功率平衡)。将点模型与一维有限差分导热系数模型耦合,以计算固体颗粒和环形圆柱形颗粒(UO_2)中的径向温度分布。后者是环形燃料棒的组成部分,在其外表面和内表面均被冷却。在热点中评估了环形和固体燃料设计的燃料,包壳和流体温度,在这种情况下,棒的最大允许额定功率比平均值高2.5倍。假定在瞬变之前,(a)带有环形燃料的反应堆在堆芯入口处比带有固体燃料的参考堆(100)以更高的标称功率(150%)和更高的标称冷却剂流速(150%)连续运行。 %)和(b)改进型和参考型反应堆在堆芯入口处具有相同的冷却剂温度,并且沿堆芯具有相同的冷却剂温升。这些条件对应于参考电抗器的150%功率提升率。耦合模型仅需要有限的计算资源。计算结果表明,在瞬态过程中,环形燃料芯块中的温度达到峰值,即使功率为150%时也比固体颗粒中100%功率时的峰值低得多。这些评估表明,在分析反应性瞬变的情况下,从两侧冷却的环形燃料比仅在其外表面冷却的固体燃料具有更好的安全性能。

著录项

  • 来源
    《Nuclear Technology》 |2014年第2期|109-126|共18页
  • 作者单位

    Federal University of Rio de Janeiro, Polytechnic School, Department of Nuclear Engineering, Av. Horacio Macedo 2030, Bloco G, Sala 206, Cidade Universitaria, 21941-914 Rio de Janeiro, RJ,Brazil;

    Federal University of Rio de Janeiro, Polytechnic School, Department of Nuclear Engineering, Av. Horacio Macedo 2030, Bloco G, Sala 206, Cidade Universitaria, 21941-914 Rio de Janeiro, RJ,Brazil;

    Federal University of Rio de Janeiro, COPPE, Graduate Engineering Program, Av. Horacio Macedo 2030, Bloco G, Sala 206, Cidade Universitdria, 21941-914 Rio de Janeiro, RJ, Brazil;

    Federal University of Rio de Janeiro, COPPE, Graduate Engineering Program, Av. Horacio Macedo 2030, Bloco G, Sala 206, Cidade Universitdria, 21941-914 Rio de Janeiro, RJ, Brazil;

  • 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
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  • 入库时间 2022-08-18 00:43:11

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