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Assessment of Severe Accident Management for Small IPWR under an ESBO Scenario
المؤلفون المشاركون
المصدر
Science and Technology of Nuclear Installations
العدد
المجلد 2019، العدد 2019 (31 ديسمبر/كانون الأول 2019)، ص ص. 1-10، 10ص.
الناشر
Hindawi Publishing Corporation
تاريخ النشر
2019-08-25
دولة النشر
مصر
عدد الصفحات
10
الملخص EN
Interest in evaluation of severe accidents induced by extended station blackout (ESBO) has significantly increased after Fukushima.
In this paper, the severe accident process under the high and low pressure induced by an ESBO for a small integrated pressurized water reactor (IPWR)-IP200 is simulated with the SCDAP/RELAP5 code.
For both types of selected scenarios, the IP200 thermal hydraulic behavior and core meltdown are analyzed without operator actions.
Core degradation studies firstly focus on the changes in the core water level and temperature.
Then, the inhibition of natural circulation in the reactor pressure vessel (RPV) on core temperature rise is studied.
In addition, the phenomena of core oxidation and hydrogen generation and the reaction mechanism of zirconium with the water and steam during core degradation are analyzed.
The temperature distribution and time point of the core melting process are obtained.
And the IP200 severe accident management guideline (SAMG) entry condition is determined.
Finally, it is compared with other core degradation studies of large distributed reactors to discuss the influence of the inherent design characteristics of IP200.
Furthermore, through the comparison of four sets of scenarios, the effects of the passive safety system (PSS) on the mitigation of severe accidents are evaluated.
Detailed results show that, for the quantitative conclusions, the low coolant storage of IP200 makes the core degradation very fast.
The duration from core oxidation to corium relocation in the lower-pressure scenario is 53% faster than that of in the high-pressure scenario.
The maximum temperature of liquid corium in the lower-pressure scenario is 134 K higher than that of the high-pressure scenario.
Besides, the core forms a molten pool 2.8 h earlier in the lower-pressure scenario.
The hydrogen generated in the high-pressure scenario is higher when compared to the low-pressure scenario due to the slower degradation of the core.
After the reactor reaches the SAMG entry conditions, the PSS input can effectively alleviate the accident and prevent the core from being damaged and melted.
There is more time to alleviate the accident.
This study is aimed at providing a reference to improve the existing IPWR SAMGs.
نمط استشهاد جمعية علماء النفس الأمريكية (APA)
Yu, Hao& Peng, Minjun. 2019. Assessment of Severe Accident Management for Small IPWR under an ESBO Scenario. Science and Technology of Nuclear Installations،Vol. 2019, no. 2019, pp.1-10.
https://search.emarefa.net/detail/BIM-1210809
نمط استشهاد الجمعية الأمريكية للغات الحديثة (MLA)
Yu, Hao& Peng, Minjun. Assessment of Severe Accident Management for Small IPWR under an ESBO Scenario. Science and Technology of Nuclear Installations No. 2019 (2019), pp.1-10.
https://search.emarefa.net/detail/BIM-1210809
نمط استشهاد الجمعية الطبية الأمريكية (AMA)
Yu, Hao& Peng, Minjun. Assessment of Severe Accident Management for Small IPWR under an ESBO Scenario. Science and Technology of Nuclear Installations. 2019. Vol. 2019, no. 2019, pp.1-10.
https://search.emarefa.net/detail/BIM-1210809
نوع البيانات
مقالات
لغة النص
الإنجليزية
الملاحظات
Includes bibliographical references
رقم السجل
BIM-1210809
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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