کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
297428 | 511756 | 2011 | 10 صفحه PDF | دانلود رایگان |

Core bypass flow in VHTR is one of the key issues for core thermal margins and efficiency. The bypass flow in the prismatic core varies during core cycles due to the irradiation shrinkage/swelling and thermal expansion of the graphite blocks. A procedure to evaluate the local gap size variation between graphite blocks was developed and applied to a prismatic core VHTR. The influence of the core restraint mechanism on the bypass flow gap was evaluated. The predicted gap size is as much as 8 mm when the graphite block is exposed to its allowable limit of fast neutron fluence. The analysis for the core bypass flow and hot spot was carried out based on the calculated gap distributions. The results indicate that the bypass gap and flow distributions are closely related to the local hot spot and its location and the core restraint mechanism preventing outward movement of the graphite block by a fastening device reduces the bypass gap size, which results in the decrease of maximum fuel temperature not less than 100 °C, when compared to the case without it.
► A procedure to evaluate the local gap size variation between graphite blocks was developed and applied to a prismatic core VHTR.
► The analysis for the core bypass flow and hot spot was carried out based on the calculated gap distributions.
► The predicted gap size is large enough to affect the flow distribution in the core.
► The bypass gap and flow distributions are closely related to the local hot spot temperature and its location.
► The core restraint mechanism preventing outward movement of graphite block reduces the bypass gap size and hot spot temperature.
Journal: Nuclear Engineering and Design - Volume 241, Issue 8, August 2011, Pages 3076–3085