An efficient method for solving flow field in high temperature gas-cooled reactor
H Zhang, B Tan, D She, L Shi - Progress in Nuclear Energy, 2025 - Elsevier
In thermal-hydraulic analysis of pebble-bed high temperature gas-cooled reactor (HTR), the
flow field calculation is a crucial and time-consuming process. It can be treated as a …
flow field calculation is a crucial and time-consuming process. It can be treated as a …
Validation of a MELCOR model of HTR-10 in normal operation and accident conditions
EM Duchnowski, NR Brown - Nuclear Engineering and Design, 2024 - Elsevier
We apply the thermal-hydraulics accident progression tool, MELCOR, to thermal–hydraulic
benchmark problems on the 10 MW High Temperature Gas-cooled Reactor-Test Module …
benchmark problems on the 10 MW High Temperature Gas-cooled Reactor-Test Module …
Development of cross-section calculation module for high-temperature gas-cooled reactor engineering simulator system using an optimal model tree algorithm
K Tan, M Liu, C Wei - Annals of Nuclear Energy, 2023 - Elsevier
To improve the accuracy of reactor physics module in the high-temperature gas-cooled
reactor engineering simulator system (HTGR-ESS), a more accurate cross-section …
reactor engineering simulator system (HTGR-ESS), a more accurate cross-section …
Transient coupling analysis of loss-of-coolant accidents in HTR-PM based on CFD approaches
Pressurized loss of forced cooling (PLOFC) and depressurized loss of forced cooling
(DLOFC) are two important accidents in high temperature gas-cooled reactors. In the …
(DLOFC) are two important accidents in high temperature gas-cooled reactors. In the …
[HTML][HTML] 球床式高温气冷堆堆芯三维建模及稳态热工水力分析
张双宝， 李良星， 谢伟， 王凯琳 - 2020 - html.rhhz.net
准确可靠的反应堆热工水力分析对球床模块式高温气冷堆的设计及安全运行具有重要意义.
基于氦气冷却剂在高温气冷堆堆芯的流动和传热进程, 利用CFD 软件构建高温气冷堆堆芯的 …
基于氦气冷却剂在高温气冷堆堆芯的流动和传热进程, 利用CFD 软件构建高温气冷堆堆芯的 …
Reverse Engineering Program Using MBSE to Support Development of I&C System Experimental Power Reactor from PLC to FPGA.
Abstract Indonesian Experimental Power Reactor (RDE) basic design is designed by refer to
the High Temperature Gas-cooled reactor-test Module (HTR-10) type which developed by …
the High Temperature Gas-cooled reactor-test Module (HTR-10) type which developed by …
The evaluation of fundamental safety function and defence in depth of AP1000 using probabilistic analysis
DTS Tjahyani, JH Purba, AS Ekariansyah… - AIP Conference …, 2024 - pubs.aip.org
The nuclear reactor is designed following the concept of defence in depth (DiD). To ensure
the adequacy of the concept is applied in the design, the fundamental safety function can be …
the adequacy of the concept is applied in the design, the fundamental safety function can be …
Research on Influence of Different Simulation Methods of Bypass Flow in Thermal Hydraulic Analysis on Temperature Distribution in HTR‐10
S Sun, Y Zhang, Y Zheng - Science and Technology of Nuclear …, 2020 - Wiley Online Library
In pebble‐bed high temperature gas‐cooled reactor, gaps widely exist between graphite
blocks and carbon bricks in the reactor core vessel. The bypass helium flowing through the …
blocks and carbon bricks in the reactor core vessel. The bypass helium flowing through the …
Three-dimensional modeling and loss-of-coolant accident analysis of high temperature gas cooled reactor
S Zhang, L Li, Z Zhang, S Zhang - Annals of Nuclear Energy, 2021 - Elsevier
The high temperature gas-cooled reactor (HTR) is well known due to its prominent inherent
safety, high efficiency and low carbon environmental protection. Accurate and reliable …
safety, high efficiency and low carbon environmental protection. Accurate and reliable …
Temperature analysis of the HTR-10 after full load rejection
XC Zhang, D She, FB Chen, L Shi, YJ Dong… - Nuclear Science and …, 2019 - Springer
The HTR-10 is a small modular high-temperature reactor located in Tsinghua University, in
China. After the reactor ran continuously for 72 h at full power in the commissioning stage, a …
China. After the reactor ran continuously for 72 h at full power in the commissioning stage, a …