ارزیابی یقینی سناریوی بازگشت برق اضطراری در حادثه هم‌زمان SB-LOCA همراه با حادثه LOOP در نیروگاه اتمی بوشهر

حسینی, سید علی; شیرانی, امیر سعید

doi:10.24200/nst.2021.1209

نوع مقاله : مقاله فنی

نویسندگان

دانشکده مهندسی هسته‌ای، دانشگاه شهید بهشتی، صندوق پستی: 1983969411، تهران - ایران

https://doi.org/10.24200/nst.2021.1209

چکیده

در دسترس بودن برق نیروگاه جهت بهره‌برداری ایمن نیروگاه‌های تجاری و بازیابی سیستم‌های ایمنی در مواقع حوادث، امری ضروری است. حادثه قطع برق خارجی نیروگاه (LOOP) یکی از حوادثی است که پس از حادثه فوکوشیما مورد توجه قرار گرفته است. اگر حادثه LOOP با روی خط آمدن دیزل ژنراتورهای واقع در سایت نیروگاه همراه نباشد، موجب وقوع حادثه قطع کامل برق نیروگاه (SBO) می‌گردد. در این مقاله حادثه هم‌زمان از دست رفتن خنک‌کننده در محدوده شکست‌های کوچک (SB-LOCA)، همراه با حادثه LOOP با در نظر گرفتن سناریو بازگشت و عدم بازگشت برق اضطراری برای شکست‌های mm 25، mm 50 و mm 100 با استفاده از کد ترموهیدرولیک RELAP5، مورد ارزیابی قرار گرفته است. همچنین در ارزیابی سناریوی بازگشت برق اضطراری صورت گرفته، بازیابی برق نیروگاه در ساعت اول و دوم مورد بررسی قرار گرفته است. نتایج حاصل از این شبیه‌سازی نشان داد که در ساعت اول بازیابی برق اضطراری، قلب رآکتور در هر سه شکست در آستانه آسیب به سوخت قرار نمی‌گیرد. این در حالیاست که در ساعت دوم بازیابی برق اضطراری، قلب رآکتور پیش از روی کار آمدن دیزل ژنراتور‌های اضطراری برای شکست‌های mm 25 و mm 50، در آستانه ذوب قرار می‌گیرد. بنابراین نتایج به دست آمده نشان می‌دهد که در محدوده شکست‌های کوچک در شرایط نبود برق نیروگاه، حداقل تا ساعت اول فرصت جهت بازیابی برق اضطراری و سیستم‌های ایمنی وجود دارد.

کلیدواژه‌ها

20.1001.1.17351871.1400.42.2.15.3

عنوان مقاله [English]

Deterministic analysis of emergency AC power recovery during SB-LOCA along with LOOP accident in Bushehr nuclear power plant

نویسندگان [English]

S.A. Hosseini
A.S. Shirani

Faculty of Engineering, Shahid Beheshti University, P.O.Box: 1983969411, Tehran – Iran

چکیده [English]

The availability of current AC electrical power is essential for the safe operation and accident recovery of commercial nuclear power plants. Loss of offsite power (LOOP) considers as one of the significant post-Fukushima accidents. When the onsite diesel generators are not recovered in the power plant, the accident encounters with station blackout (SBO) situation. In this study, the emergency AC power recovery is investigated during SB-LOCA along with LOOP accident for 25 mm, 50 mm, and 100 mm breaks with RELAP5 thermal-hydronic. Likewise, in evaluating the emergency power recovery scenario, the power plant's recovery in the first and second hours has been investigated. The results showed that in the first hour of emergency power recovery, the reactor is not reached the core damage threshold in all three breaks. Meanwhile, in the second hour of emergency power recovery for 25 mm and 50 mm, the reactor core reaches to core damage threshold before the emergency diesel generators are activated. Therefore, the results show that in SB-LOCAs with a lack of emergency power recovery, there is a chance to recover emergency power and safety systems at least until the first hour.

کلیدواژه‌ها [English]

Bushehr nuclear power plant
Deterministic safety assessment
SB-LOCA
Loss of offsite power
Station black-out
RELAP5

مراجع

1. E. Zio, Integrated deterministic and probabilistic safety assessment: concepts, challenges, research directions. Nucl. Eng. Des. 280, 413-419 (2014).

2. IAEA. Considerations on the Application of the IAEA Safety Requirements for the Design of Nuclear Power Plants. IAEA Tecdoc Series No. 1791, Vienna, (2016).

3. S.A. Eide, et al, Reevaluation of station blackout risk at nuclear power plants (NUREG/CR-6890), in Analysis of Loss of Offsite Power Events: 1986–2004, Vol. 1, US Nuclear Regulatory Commission, (2005).

4. M. Jabbari, K. Hadad, A. Pirouzmand, Re-assessment of station blackout accident in VVER-1000 NPP with additional measures following Fukushima accident using RELAP/Mod3.2. Annals of Nuclear Energy, 129, 316-330 (2019).

5. Z. Tabadar, G.R. Ansarifar, A. Pirouzmand, Probabilistic safety assessment of portable equipment applied in VVER-1000/V446 nuclear reactor during loss of ultimate heat sink accident for stress test program development. Progress in Nuclear Energy, 117, 103101 (2019).

6. S.A. Hosseini, et al, Re-assessment of accumulators performance to identify VVER-1000 vulnerabilities against various break sizes of SB-LOCA along with SBO. Progress in Nuclear Energy, 103145 (2019).

7. P. Groudev, ASTEC investigations of severe core damage behavior of VVER-1000 in case of loss of coolant accident along with Station-Black-Out. Nuclear Engineering and Design, 272, 237-244 (2014).

8. Atomic Energy Organization of Iran. Bushehr Nuclear Power Plant Final Safety Analysis Report (BNPP-FSAR), (2008).

9. G.D. Fletcher, R.R. Schultz, RELAP5/MOD3.3 code manual. Idaho National Engineering Laboratory Idaho, (1999).

10. A. Petruzzi, F. D'Auria, Thermal-hydraulic system codes in nulcear reactor safety and qualification procedures. Science and Technology of Nuclear Installations, (2008).

11. B.R. Sehgal, et al, Nuclear Safety in Light Water Reactors: Severe Accident Phenomenology. Academic Press, (2011).

12. D. Helton, H. Esmaili, D. Marksberry, Confirmatory Thermal-Hydraulic Analysis to Support Specific Success Criteria in the Standardized Plant Analysis Risk Models-Surry and Peach Bottom. NUREG-1953. Idaho National Laboratory, Idaho Falls. ID 83415, (2010).

مجله علوم و فنون هسته ای

ارزیابی یقینی سناریوی بازگشت برق اضطراری در حادثه هم‌زمان SB-LOCA همراه با حادثه LOOP در نیروگاه اتمی بوشهر

مراجع

مراجع

1. E. Zio, Integrated deterministic and probabilistic safety assessment: concepts, challenges, research directions. Nucl. Eng. Des. 280, 413-419 (2014).

2. IAEA. Considerations on the Application of the IAEA Safety Requirements for the Design of Nuclear Power Plants. IAEA Tecdoc Series No. 1791, Vienna, (2016).

3. S.A. Eide, et al, Reevaluation of station blackout risk at nuclear power plants (NUREG/CR-6890), in Analysis of Loss of Offsite Power Events: 1986–2004, Vol. 1, US Nuclear Regulatory Commission, (2005).

4. M. Jabbari, K. Hadad, A. Pirouzmand, Re-assessment of station blackout accident in VVER-1000 NPP with additional measures following Fukushima accident using RELAP/Mod3.2. Annals of Nuclear Energy, 129, 316-330 (2019).

5. Z. Tabadar, G.R. Ansarifar, A. Pirouzmand, Probabilistic safety assessment of portable equipment applied in VVER-1000/V446 nuclear reactor during loss of ultimate heat sink accident for stress test program development. Progress in Nuclear Energy, 117, 103101 (2019).

6. S.A. Hosseini, et al, Re-assessment of accumulators performance to identify VVER-1000 vulnerabilities against various break sizes of SB-LOCA along with SBO. Progress in Nuclear Energy, 103145 (2019).

7. P. Groudev, ASTEC investigations of severe core damage behavior of VVER-1000 in case of loss of coolant accident along with Station-Black-Out. Nuclear Engineering and Design, 272, 237-244 (2014).

8. Atomic Energy Organization of Iran. Bushehr Nuclear Power Plant Final Safety Analysis Report (BNPP-FSAR), (2008).

9. G.D. Fletcher, R.R. Schultz, RELAP5/MOD3.3 code manual. Idaho National Engineering Laboratory Idaho, (1999).

10. A. Petruzzi, F. D'Auria, Thermal-hydraulic system codes in nulcear reactor safety and qualification procedures. Science and Technology of Nuclear Installations, (2008).

11. B.R. Sehgal, et al, Nuclear Safety in Light Water Reactors: Severe Accident Phenomenology. Academic Press, (2011).

12. D. Helton, H. Esmaili, D. Marksberry, Confirmatory Thermal-Hydraulic Analysis to Support Specific Success Criteria in the Standardized Plant Analysis Risk Models-Surry and Peach Bottom. NUREG-1953. Idaho National Laboratory, Idaho Falls. ID 83415, (2010).

دوره 42، شماره 2 - شماره پیاپی 96
تیر 1400
صفحه 122-131

ارزیابی یقینی سناریوی بازگشت برق اضطراری در حادثه هم‌زمان SB-LOCA همراه با حادثه LOOP در نیروگاه اتمی بوشهر

مراجع

مراجع

1. E. Zio, Integrated deterministic and probabilistic safety assessment: concepts, challenges, research directions. Nucl. Eng. Des. 280, 413-419 (2014).

2. IAEA. Considerations on the Application of the IAEA Safety Requirements for the Design of Nuclear Power Plants. IAEA Tecdoc Series No. 1791, Vienna, (2016).

3. S.A. Eide, et al, Reevaluation of station blackout risk at nuclear power plants (NUREG/CR-6890), in Analysis of Loss of Offsite Power Events: 1986–2004, Vol. 1, US Nuclear Regulatory Commission, (2005).

4. M. Jabbari, K. Hadad, A. Pirouzmand, Re-assessment of station blackout accident in VVER-1000 NPP with additional measures following Fukushima accident using RELAP/Mod3.2. Annals of Nuclear Energy, 129, 316-330 (2019).

5. Z. Tabadar, G.R. Ansarifar, A. Pirouzmand, Probabilistic safety assessment of portable equipment applied in VVER-1000/V446 nuclear reactor during loss of ultimate heat sink accident for stress test program development. Progress in Nuclear Energy, 117, 103101 (2019).

6. S.A. Hosseini, et al, Re-assessment of accumulators performance to identify VVER-1000 vulnerabilities against various break sizes of SB-LOCA along with SBO. Progress in Nuclear Energy, 103145 (2019).

7. P. Groudev, ASTEC investigations of severe core damage behavior of VVER-1000 in case of loss of coolant accident along with Station-Black-Out. Nuclear Engineering and Design, 272, 237-244 (2014).

8. Atomic Energy Organization of Iran. Bushehr Nuclear Power Plant Final Safety Analysis Report (BNPP-FSAR), (2008).

9. G.D. Fletcher, R.R. Schultz, RELAP5/MOD3.3 code manual. Idaho National Engineering Laboratory Idaho, (1999).

10. A. Petruzzi, F. D'Auria, Thermal-hydraulic system codes in nulcear reactor safety and qualification procedures. Science and Technology of Nuclear Installations, (2008).

11. B.R. Sehgal, et al, Nuclear Safety in Light Water Reactors: Severe Accident Phenomenology. Academic Press, (2011).

12. D. Helton, H. Esmaili, D. Marksberry, Confirmatory Thermal-Hydraulic Analysis to Support Specific Success Criteria in the Standardized Plant Analysis Risk Models-Surry and Peach Bottom. NUREG-1953. Idaho National Laboratory, Idaho Falls. ID 83415, (2010).

دوره 42، شماره 2 - شماره پیاپی 96تیر 1400صفحه 122-131

دوره 42، شماره 2 - شماره پیاپی 96
تیر 1400
صفحه 122-131