کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
296275 511718 2014 17 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
The challenge of modeling fuel–coolant interaction: Part I – Premixing
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
The challenge of modeling fuel–coolant interaction: Part I – Premixing
چکیده انگلیسی


• We present the status modeling of the fuel–coolant interaction premixing stage in the computer code MC3D.
• We also propose a general state of the art, highlighting recent improvements in understanding and modeling, remaining difficulties, controversies and needs.
• We highlight the need for improving the understanding of the melt fragmentation and oxidation.
• The verification basis is presented.

Fuel–coolant interaction is a complex mixing process that can occur during the course of a severe accident in a nuclear power plant involving core melting and relocation. Under certain circumstances, a steam explosion might develop during the mixing of the melt and the water and induce a loss of integrity of the containment. Even in the absence of an explosion, studying the mixing phenomenon is also of high interest due to its strong impact on the progression of the accident (debris bed formation, hydrogen production). This article is the first of two aiming at presenting both a status of research and understanding of fuel–coolant interaction and the main characteristics of the model developed in the 3-dimensional computer code MC3D. It is devoted to the premixing phase whereas the second is related to the explosion phase. A special attention is given to major difficulties, uncertainties and needs for further improvements in knowledge and modeling. We discuss more particularly the major phenomena that are melt fragmentation and film boiling heat transfer and the challenges related to modeling melt solidification and oxidation. Some highlights related to the code verification are finally given.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Nuclear Engineering and Design - Volume 280, December 2014, Pages 511–527
نویسندگان
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