Calculation of the Heat Emission from Rod Bundles to Supercritical Pressure Steam

Kirillov P. L.

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Calculation of the Heat Emission from Rod Bundles to Supercritical Pressure Steam

机译：棒束到超临界压力蒸汽的散热量计算

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The maximum temperature of fuel-element cladding in VVER-SKD reactors, where a triangular lattice with relative spacing x = 1.1 is used, can be determined using known relations, since the Prandtl number Pr similar to 1 for superheated steam at supercritical pressure.

机译：可以使用已知的关系确定使用VVER-SKD反应堆中的燃料元素包壳的最高温度，其中使用相对间距x = 1.1的三角形晶格，因为对于超临界压力下的过热蒸汽，普朗特数Pr类似于1。

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来源
《Atomic Energy》 |2015年第4期|242-246|共5页
作者
Kirillov P. L.;
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作者单位

State Sci Ctr Russian Federat, Leipunskii Inst Phys & Power Engn GNTs RF FEI, Obninsk, Russia;

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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);
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正文语种 eng
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入库时间 2022-08-18 00:39:06

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1. Experimental study on the grid-enhanced heat transfer at supercritical Pressures in rod bundle [J] . Chen Jiayue, Xiong Zhenqin, Xiao Yao, Applied thermal engineering: Design, processes, equipment, economics . 2019,第期

机译：杆束上超临界压力网格增强热传递的实验研究
2. Computational Fluid Dynamic Simulations of Heat Transfer From a 2?×?2 Wire-Wrapped Fuel Rod Bundle to Supercritical Pressure Water [J] . Krishna Podila, Yanfei Rao Journal of nuclear engineering and radiation science . 2018,第1期

机译：计算流体动态模拟A×2×2×2线包装钢束到超临界压力水
3. Computational Fluid Dynamic Simulations of Heat Transfer From a 2?×?2 Wire-Wrapped Fuel Rod Bundle to Supercritical Pressure Water [J] . Krishna Podila, Yanfei Rao Current Pollution Reports . 2018,第1期

机译：计算流体动态模拟A×2×2×2线包装钢束到超临界压力水
4. EXPERIMENTAL STUDY OF HEAT TRANSFER TO SUPERCRITICAL PRESSURE WATER FLOWING IN A 2×2 ROD BUNDLE [C] . Han Wang, Qincheng Bi, Linchuan Wang, International conference on nuclear engineering . 2014

机译：超临界水在2×2杆束中传热的实验研究
5. The viscosity of steam at supercritical temperatures and pressures [D] . Whitelaw, James H. -1

机译：蒸汽在超临界温度和压力下的粘度
6. Assessment of heat transfer correlations in the sub-channels of proposed rod bundle geometry for supercritical water reactor [O] . Seth Kofi Debrah, Edward Shitsi, Silas Chabi, 2019

机译：评估超临界水反应堆拟议棒束几何形状子通道内的传热相关性
7. Studies on the Heat Transfer of Fluids at a Supercritical Pressure : 1st Report, Experiments of Supercritical Carbon-Dioxide and a Proposal of a Simple Calculation Method [O] . Hiroharu KATO, Ni-ichi NISHIWAKI, Masaru HIRATA 1967

机译：超临界压力下液体传热的研究：第一报告，超临界二氧化碳的实验和简单计算方法的提案
8. CRITICAL HEAT FLUX AND PRESSURE DROP TESTS WITH VERTICAL UPFLOW OF WATER IN A 20-ROD BUNDLE OF 0.695-INCH DIAMETER RODS (LWBR Development Program) [R] . K. J. Coeling 1977

机译：临界热通量和压力下降试验，在直径为0.695英寸的直径杆（RWBR开发计划）中，水的垂直向上流动

Calculation of the Heat Emission from Rod Bundles to Supercritical Pressure Steam

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