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Investigation and Assessment of the CFD for Horizontal Flow in the VHTR Core
المؤلفون المشاركون
Shengyuan, Yan
Habiyaremye, Jean Luc
Yingying, Wei
Chi Tran, Cong
المصدر
Science and Technology of Nuclear Installations
العدد
المجلد 2017، العدد 2017 (31 ديسمبر/كانون الأول 2017)، ص ص. 1-6، 6ص.
الناشر
Hindawi Publishing Corporation
تاريخ النشر
2017-10-26
دولة النشر
مصر
عدد الصفحات
6
الملخص EN
A nuclear power station using gas as a cooling medium has attracted so much attention because it offers high efficiency and greater safety.
For a nuclear station that operates at a very high temperature, a gas-cooled reactor is fueled by uranium, moderated by graphite, and customarily cooled by helium.
Nevertheless, throughout the operation, the bypass flow might be a result of a change in graphite shape that is caused by neutron damage.
Core bypass and cross flows are significant elements to consider since the cross gap set hurdles to the flow field that are capable of diverting sufficient amount of coolant from reactor core location and initiating a possible fuel overheating.
However, there is a great need to sufficiently validate this method by carrying out a thorough evaluation based on working environment analysis.
Comparing the computed results with the existing data from Groehn’s NHDA PMR-200 study was the only way to validate data.
A model simulation was performed on a two-prismatic fuel block with a cross gap to examine the gaping size effect.
Finally, the prediction methods for horizontal flow phenomena using a CFD technique and the field investigation results from the VHTR core were verified, and the identification of the horizontal flow behavior played a vital role in investigating the coolant velocity and pressure distribution in the horizontal gap.
نمط استشهاد جمعية علماء النفس الأمريكية (APA)
Shengyuan, Yan& Habiyaremye, Jean Luc& Yingying, Wei& Chi Tran, Cong. 2017. Investigation and Assessment of the CFD for Horizontal Flow in the VHTR Core. Science and Technology of Nuclear Installations،Vol. 2017, no. 2017, pp.1-6.
https://search.emarefa.net/detail/BIM-1203579
نمط استشهاد الجمعية الأمريكية للغات الحديثة (MLA)
Shengyuan, Yan…[et al.]. Investigation and Assessment of the CFD for Horizontal Flow in the VHTR Core. Science and Technology of Nuclear Installations No. 2017 (2017), pp.1-6.
https://search.emarefa.net/detail/BIM-1203579
نمط استشهاد الجمعية الطبية الأمريكية (AMA)
Shengyuan, Yan& Habiyaremye, Jean Luc& Yingying, Wei& Chi Tran, Cong. Investigation and Assessment of the CFD for Horizontal Flow in the VHTR Core. Science and Technology of Nuclear Installations. 2017. Vol. 2017, no. 2017, pp.1-6.
https://search.emarefa.net/detail/BIM-1203579
نوع البيانات
مقالات
لغة النص
الإنجليزية
الملاحظات
Includes bibliographical references
رقم السجل
BIM-1203579
قاعدة معامل التأثير والاستشهادات المرجعية العربي "ارسيف Arcif"
أضخم قاعدة بيانات عربية للاستشهادات المرجعية للمجلات العلمية المحكمة الصادرة في العالم العربي
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