SACOS-PLATE: A new thermal-hydraulic subchannel analysis code for plate type fuel assemblies

被引：3
作者：
Sun, Ruiyu [1 ,2 ,3 ]
Gui, Minyang [4 ,5 ]
Wang, Jinshun [1 ,2 ,3 ]
Chen, Ronghua [1 ,2 ,3 ]
Zhang, Kui [1 ,2 ,3 ]
Tian, Wenxi [1 ,2 ,3 ]
Qiu, Suizheng [1 ,2 ,3 ]
Su, G. H. [1 ,2 ,3 ]
机构：
[1] Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, Xian 710049, Shaanxi, Peoples R China
[2] Xi An Jiao Tong Univ, Shaanxi Key Lab Adv Nucl Energy & Technol, Xian, Peoples R China
[3] Xi An Jiao Tong Univ, State Key Lab Multiphase Flow Power Engn, Xian, Peoples R China
[4] Harbin Engn Univ, Harbin 150001, Peoples R China
[5] Harbin Engn Univ, Heilongjiang Prov Key Lab Nucl Power Syst & Equipm, Harbin, Peoples R China
来源：
ANNALS OF NUCLEAR ENERGY | 2024年 / 204卷
基金：
中国国家自然科学基金;
关键词：
SACOS-PLATE; Thermal-hydraulics of reactor core; Preliminary validation and assessment; REACTOR BENCHMARK PROBLEM; FLOW BLOCKAGE; HEAT-TRANSFER; PRESSURE-DROP; CHANNEL; REFRIGERANTS; ACCIDENT; SYSTEM;
D O I：
10.1016/j.anucene.2024.110517
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：
Over the past few decades, plate-type fuel elements have been widely used in advanced research reactors, small modular pressurized water reactors, production reactors, etc., with the advantages of compact structure arrangement, good heat transfer characteristics and high fuel consumption. Currently, a thermal-hydraulic subchannel analysis code, namely SACOS-PLATE code, was newly designed to satisfy the calculation of different types of plate fuel elements under various steady-state operating conditions. Based on the original SACOS code, this updated version modifies the flow distribution model, the plate heat conduction model, the heat distribution model as well as the flow heat transfer model, and then realizes the simulation of the special thermal-hydraulic phenomena of the fuel plate and the rectangular flow channel. In this present study, the RA-6 and Bettis experimental data was used to validate the code, and the simulation calculation was performed on the JRR-3 research reactor, which effectively proved the good computing capability of SACOS-PLATE code.
引用
收藏
页数：13
相关论文
共 59 条
[1]   Thermal hydraulic analyses of JRR-3: Code-to-code comparison of COOLOD-N2 and TMAP [J].
Albati, Mohammad A. ;
AL-Yahia, Omar S. ;
Park, Jonghark ;
Chae, Heetaek ;
Jo, Daeseong .
PROGRESS IN NUCLEAR ENERGY, 2014, 71 :1-8
[2]  
Almachi JC, Extensions of subchanflow for thermal hydraulic analysis of mtr-cores
[3]   High-Fidelity Steady-State and Transient Simulations of an MTR Research Reactor Using Serpent2/Subchanflow [J].
Almachi, Juan Carlos ;
Sanchez-Espinoza, Victor Hugo ;
Imke, Uwe .
ENERGIES, 2022, 15 (04)
[4]   Extension and validation of the SubChanFlow code for the thermo-hydraulic analysis of MTR cores with plate-type fuel assemblies [J].
Almachi, Juan Carlos ;
Sanchez-Espinoza, Victor ;
Imke, Uwe .
NUCLEAR ENGINEERING AND DESIGN, 2021, 379
[5]  
Badry FM, 2012, Using PARET Code for Analyzing Research Reactor Cores with Two Fuel Geometries
[6]   Analysis of the IAEA research reactor benchmark problem by the RETRAC-PC code [J].
Bousbia-Salah, A ;
Hamidouche, T .
NUCLEAR ENGINEERING AND DESIGN, 2005, 235 (06) :661-674
[7]   Development of a thermal-hydraulic subchannel analysis code for motion conditions [J].
Cai, Rong ;
Yue, Nina ;
Chen, Ronghua ;
Tian, W. X. ;
Su, G. H. ;
Qiu, S. Z. .
PROGRESS IN NUCLEAR ENERGY, 2016, 93 :165-176
[8]   Validation of the COTENP Code: A Steady-State Thermal-Hydraulic Analysis Code for Nuclear Reactors with Plate Type Fuel Assemblies [J].
Castellanos-Gonzalez, Duvan A. ;
Losada Moreira, Joao Manoel ;
Maiorino, Jose Rubens ;
Carajilescov, Pedro .
SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2018, 2018
[9]  
Chao J., 1980, T AM NUCL SOC, V34
[10]   Coupled neutronics/thermal hydraulics evaluation for thorium based fuels in thermal spectrum SCWR [J].
Chaudri, Khurrum Saleem ;
Tian, Wenxi ;
Su, Guanghui ;
Qiu, Suizheng .
PROGRESS IN NUCLEAR ENERGY, 2013, 68 :55-64
123456