同位素辐照组件热工水力计算与试验研究

留言板

尊敬的读者、作者、审稿人, 关于本刊的投稿、审稿、编辑和出版的任何问题, 您可以本页添加留言。我们将尽快给您答复。谢谢您的支持!

姓名

邮箱

手机号码

标题

留言内容

验证码

Thermal-Hydraulic Calculation and Test for Irradiation Target Assembly

Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, Mianyang, Sichuan, 621900, China

摘要: 采用数值模拟方法建立了同位素辐照组件的几何模型和数学模型,利用COBRAⅢC/MIT程序计算了同位素辐照组件的热工水力参数,并与试验结果进行了分析比较。计算得出辐照组件表面和中心最高温度分别为66.6℃和72.7℃,小于设计限值80℃;辐照组件热通道最小偏离泡核沸腾比为5.72,大于其设计限值1.5。分析结果证明,同位素辐照组件入堆辐照的热工安全性能满足要求。
- 辐照组件 /
- 热工水力 /
- COBRAⅢC/MIT程序
Abstract: In the paper, the geometry and mathematics model of the irradiation Target Assembly are built.COBRAⅢ C/MIT cod is used to calculate the flow rate and pressure drop curve of the irradiation Target Assembly, and the error of theoretic result and hydraulic test is 1.32%. The maximum temperatures on the surface and core of Irradiation Target Assembly are 66.6℃ and 72.7℃, which are less than the design limited value. The MDNBR（minimum departure from nucleate boiling ratio） is also calculated in the paper, which is 5.72 and more than the design limited value. The calculation result has significance for the safety analysis of Irradiation Target Assembly.
- Irradiation target assembly /
- Thermal hydraulic /
- COBRAⅢC/MIT code