| CASTA-1:水堆全堆芯和子通道三维两流体瞬态分析程序 |
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| 引用本文： | 傅钢,赵兆颐,曹栋兴.CASTA-1:水堆全堆芯和子通道三维两流体瞬态分析程序[J].清华大学学报(自然科学版),1986(1). |
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| 作者姓名： | 傅钢 赵兆颐 曹栋兴 |
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| 作者单位： | 工程物理系
(傅钢，赵兆颐)，工程物理系 (曹栋兴) |
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| 摘 要： | 本文给出了用于核反应堆堆芯热工水力瞬态分析的两流体模型。该模型分别列出每一相的质量、动量和能量差分守恒方程，不需要两相有相同的速度和温度。按该模型编制的ＣＡＳＴＡ－１程序能求解直角座标系的三维方程组。该程序允许选择堆芯顶部和底部的压力或速度边界条件的任意组合。由于该程序还考虑了测边界条件的处理，因此它不仅能用于全堆芯分析，还能用于子通道分析。文中还给出了压水堆和沸水堆堆芯计算实例的比较。
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| 关 键 词： | 反应堆 两流体模型 三维程序 全堆芯 子通道 热工水力 |
CASTA-1: Core-wide and Subchannel Three-dimensional Two-fluid Transient Analysis Code for Water Reactors |
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| Fu Gang,Zhao Zhaoyi,Cao Dongxing.CASTA-1: Core-wide and Subchannel Three-dimensional Two-fluid Transient Analysis Code for Water Reactors[J].Journal of Tsinghua University(Science and Technology),1986(1). |
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| Authors: | Fu Gang Zhao Zhaoyi Cao Dongxing |
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| Institution: | Department of Engineering Physics |
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| Abstract: | This paper presents a two-fluid model applied in thermal hydraulic transient analysis of nuclear reactor cores. This model involves separate partial differential equations expressing conservations of mass, momentum, and energy for each individuel fluid phase, it does not require the phases to move with the same velocity or to have equal temperatures. CASTA-1 code using this model solves the three-dimensional equations in rectangular coordinates. This code offers the choice of either pressure or velocity boundary conditions at the top and bottom of the core. Since the CASTA-1 code also includes the treatment of transverse boundary conditions, it not only can be applied in core-wide analysis, but also in subchannel analysis. The comparison of the computational results for reactor core of PWR and BWR are also presented. |
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| Keywords: | reactor two-fluid model 3D-code core-wide subchannel thermal hydraulic |
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