位置：成果数据库 > 期刊 > 期刊详情页
Development of TSACO and application to Chinese HCCB TBM cooling system
  • ISSN号：0920-3796
  • 期刊名称：Fusion Engineering and Design
  • 时间：2013.11
  • 页码：2983-2990
  • 相关项目：先进核能系统热工、物理及其耦合
作者： Wang, Jie|Tian, Wenxi|Su, Guanghui|Qiu, Suizheng|
同期刊论文项目
先进核能系统热工、物理及其耦合
期刊论文 55 会议论文 24 著作 2
同项目期刊论文
An improved mechanistic critical heat flux model and its application to motion conditions
Development of a thermal-hydraulic analysis software for a passive residual heat removal system
Development of VTSAS 1.0 and application to an IPWR
Preliminary transient thermal-hydraulic analysis for new coated UN and UC fuel options in SCWR
Study of traveling wave reactor (TWR) and CANDLE strategy: A review work
Three-dimensional study on steady thermohydraulics characteristics in secondary side of steam genera
Entrainment at T-junction: A review work
Development of a thermal hydraulic code for an integral reactor
Analysis of Westinghouse MB2 test using the Steam-generator Thermohydraulics Analysis code STAF
Development of CHF models for inner and outer RPV gaps in a meltdown severe accident
Comparative study on effect of air-water and steam-water mediums on liquid entrainment through ADS-4
Prediction of CHF in vertical heated tubes based on CFD methodology
The development of a zirconium oxidation calculating program module for Module In-vessel Degraded An
Study on secondary side flow of steam generator with coupled heat transfer from primary to secondary
Severe accident analysis for a typical PWR using the MELCOR code
Research on the leak-rate characteristics of leak-before-break (LBB) in pressurized water reactor (P
Development of a transient thermal-hydraulic code for analysis of China Demonstration Fast Reactor
Preliminary design study of a board type radial fuel shuffling sodium cooled breed and burn reactor
CFD analysis on subcooled boiling phenomena in PWR coolant channel
Minor actinide transmutation in a board type sodium cooled breed and burn reactor core
Preliminary safety analysis of the PWR with accident-tolerant fuels during severe accident condition
Effects of turbulence models on forced convection subcooled boiling in vertical pipe
COPRA experiments on natural convection heat transfer in a volumetrically heated slice pool with hig
钠冷行波堆TP-1瞬态安全分析
Analysis of PWR RPV lower head SBLOCA scenarios with the failure of high-pressure injection system u
Preliminary study of coupling CFD code FLUENT and system code RELAP5
Comparison of CORA & MELCOR core degradation simulation and the MELCOR oxidation model
Analysis of the loss of pool cooling accident in a PWR spent fuel pool with MAAP5
Depressurization study of supercritical fluid blowdown from simple vessel
Thermal-hydraulic design of water-cooled pressure tube blanket for a fusion driven subcritical react
Experimental study on spray characteristics of pressure-swirl nozzles in pressurizer
Analysis of accidental loss of pool coolant due to leakage in a PWR SFP
Effects of power level on thermal-hydraulic characteristics of steam generator
Development of a MCNP-ORIGEN burn-up calculation code system and its accuracy assessment
A theoretical CHF model for downward facing surfaces and gaps under saturated boiling
基于多孔介质模型的行波堆TP-1堆芯稳态温度场与流场数值模拟
径向和轴向倒料行波堆概念设计研究
TOPAZ-Ⅱ改进型热管辐射换热器传热单元数值研究
硬壳对熔融池换热特性影响试验研究
遗传神经网络对水平通道流动沸腾传热系数的预测
压水堆蒸汽发生器一、二次侧稳态流场耦合分析
蒸汽发生器传热管束过冷沸腾区两相流动数值模拟
耦合一、二次侧换热的蒸汽发生器二次侧流场分析
基于多孔介质模型的压水堆堆芯温场数值模拟
压水堆燃料棒束通道内过冷沸腾分析