超临界水冷堆燃料棒性能分析程序适用性研究

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

Preliminary Study on SCWR Fuel Rod Performance Analysis Code

Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610041, China

摘要: 根据超临界水冷堆(SCWR)燃料棒的热工水力特点,基于压水堆(PWR)燃料棒性能分析程序的理论模型和计算方法研究燃料包壳的物性模型和超临界水(SCW)与燃料包壳的传热模型,建立适用于SCWR燃料棒的性能分析程序——SCWRFPA。采用SCWRFPA和可分析SCWR的热工水力子通道程序ATHAS分别对1/8欧洲超临界轻水堆(HPLWR)燃料组件燃料棒进行计算,其计算结果基本一致。
- 超临界水冷堆(SCWR) /
- 燃料棒 /
- 分析程序
Abstract: A SCWR fuel rod performance analysis code is developed in this paper,based on a PWR fuel rod performance analysis code,by analyzing its model and calculation method.The new code is developed on the basis of intensive analyses of SCWR characteristics,focused on the coolant-fuel rod outside surface heat transfer and cladding properties model.Lastly,the performance analysis code was successfully tested on fuel rod of 1/8 HPLWR fuel assembly,then the paper compares the results with that from the sub-channel analysis code ATHAS,which shows that the error is small.
- Supercritial Water-Cooled Reactor（SCWR） /
- Fuel rod /
- Code study