Reliability evaluation of secondary support structure in hypothetical drop of reactor core barrel assembly

2019 ◽  
Vol 353 ◽  
pp. 110219 ◽  
Author(s):  
Yanhui Li ◽  
Jin Jiang
Keyword(s):  
Reactor Core ◽  
Reliability Evaluation ◽  
Support Structure ◽  
Secondary Support

Safety Analysis of Tunnel in Gob of High Steep Thick Coal Seam (II) - 3-D Numerical Simulation for Mechanics of Initial and Secondary Support Structure

2011 ◽  
Vol 71-78 ◽  
pp. 1539-1545
Author(s):  
Wen Bin Lu ◽  
Yi Min Wu ◽  
Jie Chen ◽  
He Lin Fu
Keyword(s):  
Numerical Simulation ◽  
Coal Seam ◽  
Treatment Plan ◽  
Three Dimensional ◽  
Axial Direction ◽  
Tunnel Structure ◽  
Support Structure ◽  
Thick Coal Seam ◽  
Highway Tunnel ◽  
Secondary Support

Taking Wusongshan Tunnel in Tongling City as an example, three-dimensional numerical simulation of new large span highway tunnel built directly through gob of steep coal seam is carried out to study the response of tunnel structure induced by mining. The results showed that, (1) Though immediately backfilling after extraction can prevent the tunnel structure from impact of mining below the tunnel, it is still necessary to forbid extraction below the tunnel consildering the duration time of the extraciton and backfilling activity. (2) Considering the long-term settlement of gob of steep coal seam, net height of the tunnel should be enlarged 50cm to ensure enough space for operation. (3) The tensile and pressive stress of the support structure in the bottom and roof section of the gob are obviously high than other, so comperihencive measures should be taken to reinforce the structure, especially to increase the tensile strength in axial direction. (4) Fortification intensity can be reduced but the fortification should be enlarged if the continuous reinforcement by steel bar is used at the radial construction joints. Based on these results, treatment plan were developed for Wusongshan Tunnel, which can also be refered for other similar projects.

Point Defect Absorption and Dislocation Loop Formation at Grain Boundaries in Hvem-Irradiated Zr and Its Alloys:1. Influence of Solute Addition

1985 ◽  
Vol 43 ◽  
pp. 350-351
Author(s):  
R.A. Herring ◽  
M. Griffiths ◽  
M.H Loretto ◽  
R.E. Smallman
Keyword(s):  
Grain Boundary ◽  
Grain Boundaries ◽  
Point Defect ◽  
Reactor Core ◽  
Solute Concentration ◽  
Nuclear Industry ◽  
Dislocation Loops ◽  
Loop Formation ◽  
Component Material ◽  
Impurity Interaction

Because Zr is used in the nuclear industry to sheath fuel and as structural component material within the reactor core, it is important to understand Zr's point defect properties. In the present work point defect-impurity interaction has been assessed by measuring the influence of grain boundaries on the width of the zone denuded of dislocation loops in a series of irradiated Zr alloys. Electropolished Zr and its alloys have been irradiated using an AEI EM7 HVEM at 1 MeV, ∼675 K and ∼10-6 torr vacuum pressure. During some HVEM irradiations it has been seen that there is a difference in the loop nucleation and growth behaviour adjacent to the grain boundary as compared with the mid-grain region. The width of the region influenced by the presence of the grain boundary should be a function of the irradiation temperature, dose rate, solute concentration and crystallographic orientation.

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