کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
297458 | 511757 | 2012 | 8 صفحه PDF | دانلود رایگان |

This paper describes the computational modeling and simulation of graphite pebbles in frictional contacts as anticipated in a pebble bed reactor. For the high temperature gas-cooled reactor, the potential dust generation from frictional contact at the surface of pebbles and the subsequent lift-off and transport of dust and absorbed fission products are of safety concern at elevated temperatures under an air ingress accident. The aim of this work is to perform a computational study to estimate the quantity of the nuclear grade graphite dust produces from a typical anticipated configuration.
► Finite element analysis of frictional contact.
► Plasticity taken into account for nuclear graphite at room temperature.
► Prediction of order of magnitude for dust loading in PBRs.
► Archard wear model for wear mass calculations.
Journal: Nuclear Engineering and Design - Volume 243, February 2012, Pages 33–40