Statistical temperature distribution calculation in pebble-bed reactors

1969 ◽  
Vol 10 (3) ◽  
pp. 367-372 ◽  
Author(s):  
L. Massimo
2020 ◽  
Vol 2020 ◽  
pp. 1-8
Author(s):  
Shiyan Sun ◽  
Youjie Zhang ◽  
Yanhua Zheng

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 gaps affects the flow distribution of the core and weakens the effective cooling of the core by helium, which in turn affects the temperature distribution and the safety features of the reactor. In this paper, the thermal hydraulic analysis models of HTR-10 with bypass flow channels simulated at different positions are designed based on the flow distribution scheme of the original core models and combined with the actual position of the core bypass flow. The results show that the bypass coolant flowing through the reflectors enhances the heat transfer of the nearby components efficiently. The temperature of the side reflectors and the carbon bricks is much lower with more side bypass coolant. The temperature distribution of the central region in the pebble bed is affected by the bypass flow positions slightly, while that of the peripheral area is affected significantly. The maximum temperature of the helium, the surface, and center of the fuel elements rises as the bypass flow ratio becomes larger, while the temperature difference between them almost keeps constant. When the flow ratio of each part keeps constant, the maximum temperature almost does not change with different bypass flow positions.


2015 ◽  
Vol 52 (7-8) ◽  
pp. 932-944 ◽  
Author(s):  
Maurice Grimod ◽  
Richard Sanchez ◽  
Frédéric Damian

2020 ◽  
Author(s):  
Donald N. Kovacic ◽  
Philip Gibbs ◽  
Logan Scott

2009 ◽  
Vol 36 (8) ◽  
pp. 1049-1058 ◽  
Author(s):  
B. Boer ◽  
J.L. Kloosterman ◽  
D. Lathouwers ◽  
T.H.J.J. van der Hagen

2011 ◽  
Vol 38 (1) ◽  
pp. 80-87 ◽  
Author(s):  
Ramatsemela Mphahlele ◽  
Abderrafi M. Ougouag ◽  
Kostadin N. Ivanov ◽  
Hans D. Gougar

2017 ◽  
Vol 2017 ◽  
pp. 1-6
Author(s):  
Jingyu Zhang ◽  
Fu Li ◽  
Yuliang Sun

The pebble-bed reactor HTR-PM is being built in China and is planned to be critical in one or two years. At present, one emphasis of engineering design is to determine the fuel management scheme of the initial core and running-in phase. There are many possible schemes, and many factors need to be considered in the process of scheme evaluation and analysis. Based on the experience from the constructed or designed pebble-bed reactors, the fuel enrichment and the ratio of fuel spheres to graphite spheres are important. In this paper, some relevant physical considerations of the initial core and running-in phase of HTR-PM are given. Then a typical scheme of the initial core and running-in phase is proposed and simulated with VSOP code, and some key physical parameters, such as the maximum power per fuel sphere, the maximum fuel temperature, the refueling rate, and the discharge burnup, are calculated. Results of the physical parameters all satisfy the relevant design requirements, which means the proposed scheme is safe and reliable and can provide support for the fuel management of HTR-PM in the future.


2010 ◽  
Vol 166 (1) ◽  
pp. 1-16 ◽  
Author(s):  
Massimiliano Fratoni ◽  
Ehud Greenspan

1992 ◽  
Vol 136 (1-2) ◽  
pp. 143-148 ◽  
Author(s):  
Kurt Kugeler ◽  
Peter-W. Phlippen ◽  
Peter Schmidtlein ◽  
Rudolf Swatoch

Carbon ◽  
1968 ◽  
Vol 6 (2) ◽  
pp. 212
Author(s):  
G Spener ◽  
M Hrovat

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