A modified system analysis code for thermo-hydraulic calculation of hydrogen in a nuclear thermal propulsion (NTP) system

被引：16

作者：

Han, Zichao ^{[1
]}

Zhang, Jing ^{[1
]}

Wang, Mingjun ^{[1
]}

Tian, Wenxi ^{[1
]}

Qiu, Suizheng ^{[1
]}

Su, G. H. ^{[1
]}

机构：

[1] Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, State Key Lab Multiphase Flow Power Engn, Shaanxi Key Lab Adv Nucl Energy & Technol, Xian 710049, Peoples R China

来源：

ANNALS OF NUCLEAR ENERGY | 2021年 / 164卷

基金：

国家重点研发计划; 中国国家自然科学基金;

关键词：

NTP; System code; Hydrogen; Thermo-hydraulic analysis;

D O I：

10.1016/j.anucene.2021.108632

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Taking advantages of long lifetime and high power density, nuclear thermal propulsion (NTP) has become an advanced propulsion option in some special power fields. Due to the high heat release and dramatic density change, the flow instability and subsequent unbalance of flow and heat transfer would happen. The thermo-hydraulic calculation of working medium is an important part of the NTP system designing work, and the system analysis methods should be developed. In this study, the system analysis code RELAP5 was modified with the thermo-physical properties, flow and heat transfer correlations of the propellant hydrogen. The modified system code has been validated against the published experiment data. The calculation results show good agreement with the experimental results and the code ELM's calculation results. The modified code was applied to thermo-hydraulic calculation of hydrogen in the analysis of a typical NTP system. The results indicate that the heat conduction between the inner and outer cores should be considered in the calculation of a two-pass NTP reactor core. This study has provided a reference for developing an NTP system analysis code. (c) 2021 Elsevier Ltd. All rights reserved.

引用

页数：11

共 26 条

[11] Uncertainty analysis of ATF Cr-coated-Zircaloy on BWR in-vessel accident progression during a station blackout [J].