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Comparative Analysis of the Dalat Nuclear Research Reactor with HEU Fuel Using SRAC and MCNP5
المؤلفون المشاركون
Tran, Hoai-Nam
Phan, Giang
Nguyen, Kien-Cuong
Tran, Viet-Phu
Hoang, Van-Khanh
Ha, Pham Nhu Viet
Kiet, Hoang Anh Tuan
المصدر
Science and Technology of Nuclear Installations
العدد
المجلد 2017، العدد 2017 (31 ديسمبر/كانون الأول 2017)، ص ص. 1-10، 10ص.
الناشر
Hindawi Publishing Corporation
تاريخ النشر
2017-12-27
دولة النشر
مصر
عدد الصفحات
10
الملخص EN
Neutronics analysis has been performed for the 500 kW Dalat Nuclear Research Reactor loaded with highly enriched uranium fuel using the SRAC code system.
The effective multiplication factors, keff, were analyzed for the core at criticality conditions and in two cases corresponding to the complete withdrawal and the full insertion of control rods.
MCNP5 calculations were also conducted and compared to that obtained with the SRAC code.
The results show that the difference of the keff values between the codes is within 55 pcm.
Compared to the criticality conditions established in the experiments, the maximum differences of the keff values obtained from the SRAC and MCNP5 calculations are 119 pcm and 64 pcm, respectively.
The radial and axial power peaking factors are 1.334 and 1.710, respectively, in the case of no control rod insertion.
At the criticality condition these values become 1.445 and 1.832 when the control rods are partially inserted.
Compared to MCNP5 calculations, the deviation of the relative power densities is less than 4% at the fuel bundles in the middle of the core, while the maximum deviation is about 7% appearing at some peripheral bundles.
This agreement indicates the verification of the analysis models.
نمط استشهاد جمعية علماء النفس الأمريكية (APA)
Phan, Giang& Tran, Hoai-Nam& Nguyen, Kien-Cuong& Tran, Viet-Phu& Hoang, Van-Khanh& Ha, Pham Nhu Viet…[et al.]. 2017. Comparative Analysis of the Dalat Nuclear Research Reactor with HEU Fuel Using SRAC and MCNP5. Science and Technology of Nuclear Installations،Vol. 2017, no. 2017, pp.1-10.
https://search.emarefa.net/detail/BIM-1203614
نمط استشهاد الجمعية الأمريكية للغات الحديثة (MLA)
Phan, Giang…[et al.]. Comparative Analysis of the Dalat Nuclear Research Reactor with HEU Fuel Using SRAC and MCNP5. Science and Technology of Nuclear Installations No. 2017 (2017), pp.1-10.
https://search.emarefa.net/detail/BIM-1203614
نمط استشهاد الجمعية الطبية الأمريكية (AMA)
Phan, Giang& Tran, Hoai-Nam& Nguyen, Kien-Cuong& Tran, Viet-Phu& Hoang, Van-Khanh& Ha, Pham Nhu Viet…[et al.]. Comparative Analysis of the Dalat Nuclear Research Reactor with HEU Fuel Using SRAC and MCNP5. Science and Technology of Nuclear Installations. 2017. Vol. 2017, no. 2017, pp.1-10.
https://search.emarefa.net/detail/BIM-1203614
نوع البيانات
مقالات
لغة النص
الإنجليزية
الملاحظات
Includes bibliographical references
رقم السجل
BIM-1203614
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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