铀氢锆动力堆堆芯燃料管理程序包开发及验证

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

Development and Verification of In-Core Fuel Management Code Package for Uranium Zirconium Hydride Power Reactor

National Key Laboratory of Reactor System Design Technology, Nuclear Power Institute of China, Chengdu, 610041, China

摘要: 介绍了基于轻水堆燃料组件参数计算程序和堆芯燃料管理程序开发的铀氢锆动力堆堆芯燃料管理程序包。采用西安脉冲堆的实测数据和国外相关研究设计参数对其进行了验证分析。结果表明:本程序包计算值与西安脉冲堆的实测数据及国外设计参数符合良好。
- 铀氢锆动力堆 /
- 堆芯燃料管理 /
- 程序包 /
- 开发 /
- 验证
Abstract: This paper introduces the in-core fuel management code package for uranium zirconium hy-dride power reactor developed on the basis of the assembly parameter and in-core fuel management calcula-tion methods for LWR.The code package is verified by the experimental data of Xi’an pulsed reactor and the design parameters of international interrelated study.The verification shows that the calculated values of thecode package are in good agreement with the experimental data and the physical design values.This code package can be used for the in-core fuel management for the uranium zirconium hydride power reactor.
- Uranium zirconium hydride power reactor /
- In-core fuel management /
- Code package /
- Development /
- Verification