Effect of initial pressure on the burning behavior of ethanol pool fire in the closed pressure vessel

Author(s):  
Jian Chen ◽  
Yanli Zhao ◽  
Yubo Bi ◽  
Changhai Li ◽  
Depeng Kong ◽  
...  
Fuel ◽  
2018 ◽  
Vol 234 ◽  
pp. 464-472 ◽  
Author(s):  
Depeng Kong ◽  
Zhen Zhang ◽  
Ping Ping ◽  
Guoming Chen ◽  
Xu He ◽  
...  

2018 ◽  
Vol 31 (5) ◽  
pp. 436-449 ◽  
Author(s):  
Depeng Kong ◽  
Zhen Zhang ◽  
Ping Ping ◽  
Xu He ◽  
Hanbing Yang

Author(s):  
Hayri Sezer ◽  
Kemal S. Arsava ◽  
Shijin P. Kozhumal ◽  
Ali S. Rangwala
Keyword(s):  

2021 ◽  
Vol 117 ◽  
pp. 104131
Author(s):  
Jiaqiang Han ◽  
Pengqiang Geng ◽  
Zihao Wang ◽  
Fei Wang ◽  
Miaocheng Weng ◽  
...  

Author(s):  
Mahesh Kumar Tiwari ◽  
Avinash Chaudhary ◽  
Akhilesh Gupta ◽  
Surendra Kumar

Author(s):  
Y. Xiang ◽  
Y. W. Wu ◽  
S. Z. Qiu ◽  
W. X. Tian ◽  
G. H. Su

Depressurization and Entrainment TEst Loop (ADETEL) modeled after AP1000 with a scaling ratio of 1:5.6 was constructed to investigate the entrainment and depressurization behavior after the actuation of ADS-4 valves. The entrainment and depressurization features were investigated under different initial pressure, mixture liquid level in the pressure vessel and heating power. The entrainment deposition effect of reactor internals was also investigated. The test data reveals that large amount of water are entrained through the ADS-4 branch line within a short period of time. The liquid entrainment rate and the reduced rate of the mixture liquid level in the pressure vessel increase with the initial system pressure. It is notable that the core uncovery was experienced when the initial pressure was set as 0.5MPa in current experimental conditions. The reactor internals have little effect on the entrained mass and the mixture liquid levels in the pressure vessel. The correlation has been fitted after the Welter.et al’ model for the entrainment onset and entrainment rate, which can be applied in RELAP5 as the simulation investigation.


1986 ◽  
Vol 84 ◽  
Author(s):  
M.D. Merz ◽  
F. Gerber ◽  
R. Wang

AbstractThe Materials Characterization Center (MCC) at Pacific Northwest Lab- oratory is performing three kinds of corrosion tests for the Basalt Waste Isolation Project (BWIP) to establish the interlaboratory reproducibility and uncertainty of corrosion rates of container materials for high-level nuclear waste. The three types of corrosion tests were selected to address two distinct conditions that are expected in a repository constructed in basalt. An air/steam test is designed to address corrosion during the operational period and static pressure vessel and flowby tests are designed to address corrosion under conditions that bound the condi ring the post-closure period of the repository.The results of tests at reference testing conditions, which were defined to facilitate interlaboratory comparison of data, are presented. Data are reported for the BWIP/MCC-105.5 Air/Steam Test, BWIP/MCC-105.1 Static Pressure Vessel, and BWIP/MC-105.4 Flowby Test. In those cases where data are available from a second laboratory, a statistical analysis of interlaboratory results is reported and expected confidence intervals for mean corrosion rates are given. Other statistical treatment of data include analyses of the effects of vessel-to-vessel variations, test capsule variations for the flowby test, and oven-to-oven variations for air/steam tests.


Author(s):  
Kenneth K. Kuo ◽  
Yeu-Cherng Lu ◽  
Y. J. Yim ◽  
F. R. Schwam

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