Multiphysics Modeling and Validation of Spent Fuel Isotopics Using Coupled NeutronicsThermal-Hydraulics Simulations
المؤلفون المشاركون
Price, Dean
Radaideh, Majdi I.
Mui, Travis
Katare, Mihir
Kozlowski, Tomasz
المصدر
Science and Technology of Nuclear Installations
العدد
المجلد 2020، العدد 2020 (31 ديسمبر/كانون الأول 2020)، ص ص. 1-14، 14ص.
الناشر
Hindawi Publishing Corporation
تاريخ النشر
2020-07-26
دولة النشر
مصر
عدد الصفحات
14
الملخص EN
Multiphysics coupling of neutronics/thermal-hydraulics models is essential for accurate modeling of nuclear reactor systems with physics feedback.
In this work, SCALE/TRACE coupling is used for neutronic analysis and spent fuel validation of BWR assemblies, which have strong coolant feedback.
3D axial power profiles with coolant feedback are captured in these advanced simulations.
The methodology is applied to two BWR assemblies (2F2DN23/SF98 and 2F2D1/F6), discharged from the Fukushima Daini-2 unit.
Coupling is performed externally, where the SCALE/T5-DEPL module transfers axial power data in all axial nodes to TRACE, which in turn calculates the coolant density and temperature for each of these nodes.
Within a burnup step, the data exchange process is repeated until convergence of all coupling parameters (axial power, coolant density, and coolant temperature) is observed.
Analysis of axial power, criticality, and coolant properties at the assembly level is used to verify the coupling process.
The 2F2D1/F6 benchmark seems to have insignificant void feedback compared to 2F2DN23/SF98 case, which experiences large power changes during operation.
Spent fuel isotopic data are used to validate the coupling methodology, which demonstrated good results for uranium isotopes and satisfactory results for other actinides.
This work has a major challenge of lack of documented data to build the coupled models (boundary conditions, control rod history, spatial location in the core, etc.), which encourages more advanced methods to approximate such missing data to achieve better modeling and simulation results.
نمط استشهاد جمعية علماء النفس الأمريكية (APA)
Price, Dean& Radaideh, Majdi I.& Mui, Travis& Katare, Mihir& Kozlowski, Tomasz. 2020. Multiphysics Modeling and Validation of Spent Fuel Isotopics Using Coupled NeutronicsThermal-Hydraulics Simulations. Science and Technology of Nuclear Installations،Vol. 2020, no. 2020, pp.1-14.
https://search.emarefa.net/detail/BIM-1209427
نمط استشهاد الجمعية الأمريكية للغات الحديثة (MLA)
Price, Dean…[et al.]. Multiphysics Modeling and Validation of Spent Fuel Isotopics Using Coupled NeutronicsThermal-Hydraulics Simulations. Science and Technology of Nuclear Installations No. 2020 (2020), pp.1-14.
https://search.emarefa.net/detail/BIM-1209427
نمط استشهاد الجمعية الطبية الأمريكية (AMA)
Price, Dean& Radaideh, Majdi I.& Mui, Travis& Katare, Mihir& Kozlowski, Tomasz. Multiphysics Modeling and Validation of Spent Fuel Isotopics Using Coupled NeutronicsThermal-Hydraulics Simulations. Science and Technology of Nuclear Installations. 2020. Vol. 2020, no. 2020, pp.1-14.
https://search.emarefa.net/detail/BIM-1209427
نوع البيانات
مقالات
لغة النص
الإنجليزية
الملاحظات
Includes bibliographical references
رقم السجل
BIM-1209427
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