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Analysis of Control Rod Drop Accidents for the Canadian SCWR Using Coupled 3-Dimensional Neutron Kinetics and Thermal Hydraulics
المؤلفون المشاركون
Novog, David R.
Salaun, Frederic
المصدر
Science and Technology of Nuclear Installations
العدد
المجلد 2018، العدد 2018 (31 ديسمبر/كانون الأول 2018)، ص ص. 1-17، 17ص.
الناشر
Hindawi Publishing Corporation
تاريخ النشر
2018-01-22
دولة النشر
مصر
عدد الصفحات
17
الملخص EN
The Canadian Supercritical Water-cooled Reactor (SCWR), a GEN IV reactor design, is a hybrid design of the well-established CANDU™ and Boiling Water Reactor with water above its thermodynamic critical point.
Given the batch fueled design, control rods are used to manage the reactivity throughout the fuel cycle.
This paper examines the consequences of a control rod drop accident (CRDA) for the Canadian SCWR.
The asymmetry generated by the dropped rod requires an accurate 3-dimensional neutron kinetics calculation coupled to a detailed thermal-hydraulic model.
Before simulating the CRDAs, the proper implementation of the 3D reactivity feedback was verified and various sensitivity studies were performed.
This work demonstrates that the proposed safety systems for the SCWR core are capable of terminating the CRDA sequence prior to exceeding maximum sheath and centerline temperatures.
In one instance involving a rod on the periphery of the core, the proposed trip setpoint (115% FP) was not exceeded and a new steady state was reached.
Therefore it is recommended that the design also include provisions for a high-log rate and/or local Neutron Overpower Protection (NOP) trips, similar to existing CANDU designs such that reactor shutdown can be assured for such spatial anomalies.
نمط استشهاد جمعية علماء النفس الأمريكية (APA)
Salaun, Frederic& Novog, David R.. 2018. Analysis of Control Rod Drop Accidents for the Canadian SCWR Using Coupled 3-Dimensional Neutron Kinetics and Thermal Hydraulics. Science and Technology of Nuclear Installations،Vol. 2018, no. 2018, pp.1-17.
https://search.emarefa.net/detail/BIM-1214892
نمط استشهاد الجمعية الأمريكية للغات الحديثة (MLA)
Salaun, Frederic& Novog, David R.. Analysis of Control Rod Drop Accidents for the Canadian SCWR Using Coupled 3-Dimensional Neutron Kinetics and Thermal Hydraulics. Science and Technology of Nuclear Installations No. 2018 (2018), pp.1-17.
https://search.emarefa.net/detail/BIM-1214892
نمط استشهاد الجمعية الطبية الأمريكية (AMA)
Salaun, Frederic& Novog, David R.. Analysis of Control Rod Drop Accidents for the Canadian SCWR Using Coupled 3-Dimensional Neutron Kinetics and Thermal Hydraulics. Science and Technology of Nuclear Installations. 2018. Vol. 2018, no. 2018, pp.1-17.
https://search.emarefa.net/detail/BIM-1214892
نوع البيانات
مقالات
لغة النص
الإنجليزية
الملاحظات
Includes bibliographical references
رقم السجل
BIM-1214892
قاعدة معامل التأثير والاستشهادات المرجعية العربي "ارسيف Arcif"
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