کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
1565796 1514209 2013 11 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Modelling of irradiated UO2 fuel behaviour under transient conditions
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی انرژی هسته ای و مهندسی
پیش نمایش صفحه اول مقاله
Modelling of irradiated UO2 fuel behaviour under transient conditions
چکیده انگلیسی

On the basis of a critical assessment of the Booth-Speight model for the fission gas release from irradiated fuel, a more consistent mechanistic approach is developed for consideration of the microstructure evolution and fission gas release under conditions of power ramp tests. A new model that modifies the Nelson model for gas atom resolution from bubbles and explains the observed formation of a new population of large bubbles, is developed and implemented in the MFPR code. Superposition of various mechanisms of gas transport: gas atom diffusion, bubbles random and biased migration, and gas sweeping by grain boundaries, results in a reasonable prediction of the measured fractional gas release and microstructure evolution, observed in the ramp tests.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Journal of Nuclear Materials - Volume 437, Issues 1–3, June 2013, Pages 250–260
نویسندگان
, ,