Journal of Nuclear Science, Engineering and Technology (JONSAT)
In cooperation with the Iranian Nuclear Society

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

Document Type : Scientific Note

Authors

S.A. Hosseini
A.S. Shirani

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

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

Highlights

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).

Keywords

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

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