کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
4925435 | 1431398 | 2017 | 10 صفحه PDF | دانلود رایگان |
عنوان انگلیسی مقاله ISI
Statistical modelling of graphite brick weight loss in Advanced Gas Cooled Reactors
ترجمه فارسی عنوان
مدلسازی آماری از کاهش وزن آجر گرافیت در راکتورهای گاز خنک کننده پیشرفته
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کلمات کلیدی
گرافیت، راکتورهای پیشرفته گاز خنک کننده، اکسیداسیون، کاهش وزن، تنوع سیستم،
موضوعات مرتبط
مهندسی و علوم پایه
مهندسی انرژی
مهندسی انرژی و فناوری های برق
چکیده انگلیسی
Demonstrating the physical integrity of graphite cores in UK Advanced Gas Cooled Nuclear Reactors operated by EDF Energy (formerly British Energy) is essential to the demonstration of their continued safe operation. The cores contain around 3000 graphite bricks which are subject to cracking and weight loss due to oxidation. If too much graphite is lost by oxidation the core will cease to act as an efficient moderator for neutrons. Periodic inspections are made of parts of the core to provide information on the state of a sample of the bricks. Statistical models are routinely used to help understand the evolution of brick cracking in the reactors. In this paper details are given of the use of mixed effects statistical models for weight loss to predict what will be seen at reactor inspections. By making blind predictions of core behaviour and then comparing these with observations from inspections, the predictive performance of the models has been quantified and they are then used to produce long-term forecasts of core behaviour. A key feature of the models is the need to represent system variability at different scales. Being able to forecast core behaviour enables reactor lifetimes to be estimated which has major economic implications.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Nuclear Engineering and Design - Volume 323, November 2017, Pages 156-165
Journal: Nuclear Engineering and Design - Volume 323, November 2017, Pages 156-165
نویسندگان
P.R. Maul, P.C. Robinson, J.F. Burrow,