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Simulation of Station Black-Out in Bushehr NPP by RELAP5 Code and Comparison its Results with Those of Comissioning Test
Mohammad Beygian, Narges | 2012
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- Type of Document: M.Sc. Thesis
- Language: Farsi
- Document No: 46963 (46)
- University: Sharif University of Technology
- Department: Energy Engineering
- Advisor(s): Ghofrani, Mohammad Bagher; Talebi, Majid
- Abstract:
- The event of the loss of off-site power (loop) is one of the nuclear power plant accidents which, if occurred, in worst case , the main generator will be stopped after a short time after beginning of the accident and AC feed of the power plant loads such as safety systems and main pumps of primary circuit will be interrupted . In order to control the event, it is necessary to start the emergency diesel generators, at least for one of safety channels. If the diesel generators are not started or not loaded, the accident will advance, and it will be changed to station black-out (SBO). If the SBO occurs, due to non operation of residual heat removal systems (RHR), it may be result to melt the reactor core. In this project, based on the existing document in the final safety analysis report (FSAR) of Bushehr nuclear power plant, the occurrence of the station black-out and the systems which activated during the accident , has been modeled with RELAP code. At first, for assessment of the accuracy of the modeling, comparison between the calculated parameters in steady state conditions and nominal power and existing parameters in safety documents of power plant was made, which shows a good agreement. Then the accident of the complete loss of off-site power of Bushehr nuclear power plant was modeled using RELAP code and the results were compared with the existing data in safety reports. This study showed that opening the pressurizer safety valves and also returning the source of power for one of the related channels to high pressure and low pressure systems by operator during the event was effective in controlling the condition and getting to normal conditions. As a result, the safety barriers of the power plant were not damaged. Furthermore, there was a good agreement between the RELAP codes results and analysis in the safety analysis reports of Bushehr nuclear power plant
- Keywords:
- Nuclear Power Plants ; Steady State ; Bushehr Nuclear Power Plant ; RELAP5 Code ; Station Black-Out (SBO)Accident ; Loss of Offsite Power (LOOP)Accident
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محتواي کتاب
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- مقدمه
- معرفی حادثه قطع کامل برق وسیستمهای ایمنی مرتبط در نیروگاه اتمی بوشهر
- مدل سازی سیستمهای مرتبط با حادثه SBO با کد5 RELAP در شرایط پایدار
- معرفی کد 5 RELAP
- حجمبندی سیستمهای مرتبط با حادثه
- حجمبندی راکتور
- مدلسازی پمپها و لولههای اصلی مدار خنککننده اولیه
- حجمبندی سیستم تنظیم فشار مدار اولیه
- حجمبندی سیستم کنترل حجم و شیمی مدار اولیه TA(Chemical and Volume Control System)
- حجمبندی سیستم خنککننده اضطراری قلب راکتور
- حجمبندی مولدبخار
- مدلسازی سیستم آب تغذیه
- حجم بندی خطوط اصلی بخار
- مدلسازی شیرهای ایمنی مولدبخار SG PSD
- مدلسازی شیر خروج بخار به اتمسفر BRU-A
- شیر خروج بخار به چگالنده BRU-K
- مدلسازی شیر توقف توربین Turbine Stope Valve (TSV)
- مدلسازی ساختارهای حرارتی
- بررسی نتایج حالت پایدار
- مدل سازی حادثه قطع کامل برق نیروگاه با کد5 RELAP
- نتیجه گیری و پیشنهادات
- معرفی کد 5 RELAP
- پاسخ به سوالات اساتید
- مراجع