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首页> 外文期刊>Nuclear Technology >THE NEUTRONICS DESIGN AND ANALYSIS OF A 200-MW(ELECTRIC) SIMPLIFIED BOILING WATER REACTOR CORE
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THE NEUTRONICS DESIGN AND ANALYSIS OF A 200-MW(ELECTRIC) SIMPLIFIED BOILING WATER REACTOR CORE

机译:200兆瓦(电)简化沸水反应堆堆芯的神经网络设计与分析

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摘要

A 200-MW(electric) simplified boiling water reactor (SBWR) was designed and analyzed under sponsorship of the U.S. Department of Energy Nuclear Energy Research Initiative program. The compact size of a 200-MW(electric) reactor makes it attractive for countries with a less well developed engineering infrastructure, as well as for developed countries seeking to tailor generation capacity more closely to the growth of their electricity demand. The 200-MW (electric) core design reported here is based on the 600-MW(electric) General Electric SBWR core, which was first analyzed in the work performed here in order to qualify the computer codes used in the analysis. Cross sections for the 8 X 8 fuel assembly design were generated with the HELIOS lattice physics code, and core simulation was performed with the U.S. Nuclear Regulatory Commission codes RELAP5/PARCS. In order to predict the critical heat flux, the Hench-Gillis correlation was implemented in the RELAP5 code. An equilibrium cycle was designed for the 200-MW(electric) core, which provided a cycle length of more than 2 yr and satisfied the minimum critical power ratio throughout the core life.
机译:在美国能源部核能研究计划计划的赞助下,设计并分析了200兆瓦(电)简化沸水反应堆(SBWR)。 200兆瓦(电)反应堆的紧凑尺寸使其对工程基础设施欠发达的国家以及寻求根据发电需求的增长更紧密地调整发电量的发达国家具有吸引力。此处报告的200兆瓦(电)芯设计基于600兆瓦(电)通用电气SBWR芯,该芯首先在此处执行的工作中进行了分析,以限定分析中使用的计算机代码。使用HELIOS晶格物理代码生成8 X 8燃料组件设计的横截面,并使用美国核监管委员会代码RELAP5 / PARCS进行堆芯仿真。为了预测临界热通量,在RELAP5代码中实现了Hench-Gillis相关性。为200兆瓦(电)铁心设计了一个平衡循环,该循环提供了超过2年的循环长度,并满足了整个铁心寿命中的最小临界功率比。

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