Wear behavior of graphitic matrix of fuel elements used in pebble-bed high-temperature gas-cooled reactors against steel

2018 ◽  
Vol 328 ◽  
pp. 353-358 ◽  
Author(s):  
Bin Wu ◽  
Yue Li ◽  
Hong-sheng Zhao ◽  
Shuang Liu ◽  
Bing Liu ◽  
...  
Keyword(s):  
High Temperature ◽  
Wear Behavior ◽  
Pebble Bed ◽  
Fuel Elements ◽  
High Temperature Gas

Gas-Cooled Modular Reactors With Spherical Fuel Elements — Their Inherent Safety and Applications Not Just for Power Generation

2014 ◽  
Author(s):  
Walter Jaeger ◽  
H. J. Hamel ◽  
Heinz Termuehlen
Keyword(s):  
Power Generation ◽  
High Temperature ◽  
Reactor Design ◽  
Inherent Safety ◽  
Pebble Bed ◽  
Pebble Bed Reactor ◽  
Pebble Bed Reactors ◽  
Fuel Elements ◽  
High Temperature Gas

The gas-cooled reactor design with spherical fuel elements, referred to as high-temperature gas-cooled reactors (HTGR or HTR reactors) or pebble bed reactors has been already suggested by Farrington Daniels in the late 1940s; also referred to as Daniels’ pile reactor design. Under Rudolf Schulten the first pebble bed reactor, the 46MWth AVR Juelich reactor (Atom Versuchs-Reactor Jülich) was built in the late 1960s. It was in operation for 22 years and extensive testing confirmed its inherent safety.

The Gasification of Graphite Matrix in Pebble Bed Reactors

2009 ◽  
Author(s):  
Xinli Yu ◽  
Suyuan Yu
Keyword(s):  
High Temperature ◽  
Corrosion Rate ◽  
Fuel Element ◽  
Pebble Bed ◽  
The Core ◽  
Graphite Matrix ◽  
Matrix Graphite ◽  
Element Matrix ◽  
Fuel Elements ◽  
High Temperature Gas

This paper mainly deals with the simulations of graphite matrix of the spherical fuel elements by steam in normal operating conditions. The fuel element matrix graphite was firstly simplified to an annular part in the simulations. Then the corrosions to the matrix graphite in 10 MW High Temperature Gas-cooled Reactor (HTR-10) and the High Temperature Gas-cooled Reactor—–Pebble-bed Module (HTR-PM) were investigated respectively. The results showed that the gasification of fuel element matrix graphite was uniform and mainly occurred at the bottom of the core in both of the reactors in the mean residence time of the spherical fuel elements. This was mainly caused by the designed high temperature at the bottom. The total mass gasified in HTR-PM was much greater than the HTR-10, while it did not mean much severer corrosion occurred there. As it is known the core volume of HTR-PM is much larger than the HTR-10, which will result in much greater consumed graphite even for the same corrosion rate. The steam only lost about 1 to 3 percent after flowing through the cores in both reactors for different steam conditions. The corrosion of graphite became worse when the steam concentrations increased in helium coolant. The results also indicated that the corrosion rate of fuel element matrix graphite tended to increase slightly with the prolonging of the service time.

Steady-State Neutrbnic Investigations to the Accident of Water Ingress in Systems with Pebble-Bed High-Temperature Gas-Cooled Reactor Fuel

1987 ◽  
Vol 97 (1) ◽  
pp. 72-88 ◽  
Author(s):  
F. Schürrer ◽  
W. Ninaus ◽  
K. Oswald ◽  
R. Rabitsch ◽  
Hj. Müller ◽  
...  
Keyword(s):  
Steady State ◽  
High Temperature ◽  
Reactor Fuel ◽  
Pebble Bed ◽  
Water Ingress ◽  
High Temperature Gas

scholarly journals A review of pebble flow study for pebble bed high temperature gas-cooled reactor

2019 ◽  
Vol 1 (3) ◽  
pp. 159-176 ◽  
Author(s):  
Shengyao Jiang ◽  
Jiyuan Tu ◽  
Xingtuan Yang ◽  
Nan Gui
Keyword(s):  
High Temperature ◽  
Pebble Bed ◽  
Pebble Flow ◽  
Flow Study ◽  
High Temperature Gas

Carbon materials in a high temperature gas-cooled reactor pebble-bed module

2018 ◽  
Vol 33 (2) ◽  
pp. 97-108 ◽  
Author(s):  
Xiang-wen Zhou ◽  
Yang Yang ◽  
Jing Song ◽  
Zhen-ming Lu ◽  
Jie Zhang ◽  
...  
Keyword(s):  
High Temperature ◽  
Carbon Materials ◽  
Pebble Bed ◽  
High Temperature Gas
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