The R&D of HTR-STAC Program Package: Source Term Analysis Codes for Pebble-Bed High-Temperature Gas-Cooled Reactor
المؤلفون المشاركون
Chen, Hongyu
Li, Chuan
Fang, Chao
Xing, Haoyu
المصدر
Science and Technology of Nuclear Installations
العدد
المجلد 2018، العدد 2018 (31 ديسمبر/كانون الأول 2018)، ص ص. 1-9، 9ص.
الناشر
Hindawi Publishing Corporation
تاريخ النشر
2018-12-02
دولة النشر
مصر
عدد الصفحات
9
الملخص EN
Source term analysis is important in the design and safety analysis of advanced nuclear reactor and also provides a radiation safety analysis basis for Modular High-Temperature Gas-Cooled Reactor (HTR).
High-Temperature Gas-Cooled Reactor-Pebble-bed Modules (HTR-PM) design by China is a typical Gen-IV and due to different safety concepts and systems, the implements of source term analysis in light water reactors are not entirely applicable to HTR-PM.
To solve this problem, HTR-PM Source Term Analysis Code (HTR-STAC) has been developed and related V&V has been finished.
HTR-STAC consists of five units, including LOOP (Primary Circuit Source Term Analysis Code), NORMAL (Normal Condition Airborne Source Term Analysis Code), ARCC (Accident Release Category Calculation code), CARBON (C-14 Source Term Analysis Code), and TRUM (Tritium Source Term Analysis Code).
LOOP and NORMAL may be used as calculating primary circuit coolant radioactivity and the release of airborne radioactivity to the environment under normal operating conditions of HTR-PM, respectively.
The code ARCC composed of several source term analysis programs in the different typical accidents scenario, including SGTR (Steam Generator Tube Rupture), LOCA (Loss of Coolant Accident), and the Transient Process, is compiled based on the results given by LOOP and NORMAL.
CARBON and TRUM are developed to calculate the productions of C-14 and H-3 through a different mechanism.
Furthermore, the V&V has been performed and show some positive results.
نمط استشهاد جمعية علماء النفس الأمريكية (APA)
Chen, Hongyu& Li, Chuan& Xing, Haoyu& Fang, Chao. 2018. The R&D of HTR-STAC Program Package: Source Term Analysis Codes for Pebble-Bed High-Temperature Gas-Cooled Reactor. Science and Technology of Nuclear Installations،Vol. 2018, no. 2018, pp.1-9.
https://search.emarefa.net/detail/BIM-1214996
نمط استشهاد الجمعية الأمريكية للغات الحديثة (MLA)
Chen, Hongyu…[et al.]. The R&D of HTR-STAC Program Package: Source Term Analysis Codes for Pebble-Bed High-Temperature Gas-Cooled Reactor. Science and Technology of Nuclear Installations No. 2018 (2018), pp.1-9.
https://search.emarefa.net/detail/BIM-1214996
نمط استشهاد الجمعية الطبية الأمريكية (AMA)
Chen, Hongyu& Li, Chuan& Xing, Haoyu& Fang, Chao. The R&D of HTR-STAC Program Package: Source Term Analysis Codes for Pebble-Bed High-Temperature Gas-Cooled Reactor. Science and Technology of Nuclear Installations. 2018. Vol. 2018, no. 2018, pp.1-9.
https://search.emarefa.net/detail/BIM-1214996
نوع البيانات
مقالات
لغة النص
الإنجليزية
الملاحظات
Includes bibliographical references
رقم السجل
BIM-1214996
قاعدة معامل التأثير والاستشهادات المرجعية العربي "ارسيف Arcif"
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