Sensitivity and Uncertainty Analysis of the Maximum Fuel Temperature under Accident Condition of HTR-PM
المؤلفون المشاركون
Hao, Chen
Li, Peijun
Zhou, Xiaoyu
She, Ding
Yang, Rongrui
المصدر
Science and Technology of Nuclear Installations
العدد
المجلد 2020، العدد 2020 (31 ديسمبر/كانون الأول 2020)، ص ص. 1-21، 21ص.
الناشر
Hindawi Publishing Corporation
تاريخ النشر
2020-02-22
دولة النشر
مصر
عدد الصفحات
21
الملخص EN
The maximum fuel temperature under accident condition is the most important parameter of inherently safe characteristics of HTR-PM, and the DLOFC accident may lead to a peak accident fuel temperature.
And there are a variety of uncertainty sources in the maximum fuel temperature calculations, and thus the contributions of these uncertainty sources to the final calculated maximum fuel temperature should be quantified to check whether the peak value exceed the technological limit of 1620°C or not.
Eight uncertainty input parameters are selected for inclusion in this uncertainty study, and their associated 2 standard deviation uncertainties and probability density functions are specified.
Then, the DLOFC thermal analyses and uncertainty analysis are performed with the home-developed ATHENA and CUSA.
The numerical results indicate that the pebble-bed effective conductivity and the decay heat contribute the most of the uncertainty in the DLOFC maximum fuel temperature while this peak fuel temperature is most sensitive to the initial reactor power and the decay heat.
In short, uncertainties in these selected eight parameters lead to the two standard deviation (2σ) uncertainty of ±77.6°C (or 5.2%) around the mean value of 1493°C for the maximum fuel temperature under DLOFC accident of HTR-PM.
At the same time, the LHS-SVDC method of CUSA is recommended to propagate uncertainties in inputs and 100–200 model simulations seem to be sufficient to get an uncertainty prediction with full confidence.
نمط استشهاد جمعية علماء النفس الأمريكية (APA)
Hao, Chen& Li, Peijun& She, Ding& Zhou, Xiaoyu& Yang, Rongrui. 2020. Sensitivity and Uncertainty Analysis of the Maximum Fuel Temperature under Accident Condition of HTR-PM. Science and Technology of Nuclear Installations،Vol. 2020, no. 2020, pp.1-21.
https://search.emarefa.net/detail/BIM-1209539
نمط استشهاد الجمعية الأمريكية للغات الحديثة (MLA)
Hao, Chen…[et al.]. Sensitivity and Uncertainty Analysis of the Maximum Fuel Temperature under Accident Condition of HTR-PM. Science and Technology of Nuclear Installations No. 2020 (2020), pp.1-21.
https://search.emarefa.net/detail/BIM-1209539
نمط استشهاد الجمعية الطبية الأمريكية (AMA)
Hao, Chen& Li, Peijun& She, Ding& Zhou, Xiaoyu& Yang, Rongrui. Sensitivity and Uncertainty Analysis of the Maximum Fuel Temperature under Accident Condition of HTR-PM. Science and Technology of Nuclear Installations. 2020. Vol. 2020, no. 2020, pp.1-21.
https://search.emarefa.net/detail/BIM-1209539
نوع البيانات
مقالات
لغة النص
الإنجليزية
الملاحظات
Includes bibliographical references
رقم السجل
BIM-1209539
قاعدة معامل التأثير والاستشهادات المرجعية العربي "ارسيف Arcif"
أضخم قاعدة بيانات عربية للاستشهادات المرجعية للمجلات العلمية المحكمة الصادرة في العالم العربي
تقوم هذه الخدمة بالتحقق من التشابه أو الانتحال في الأبحاث والمقالات العلمية والأطروحات الجامعية والكتب والأبحاث باللغة العربية، وتحديد درجة التشابه أو أصالة الأعمال البحثية وحماية ملكيتها الفكرية. تعرف اكثر