Safety Analysis in VVER-1000 Due to Large-Break Loss-of-Coolant Accident and Station Blackout Transient Using RELAP5/SCDAPSIM/MOD3.5

References

• “ Safety of Nuclear Power Plants: Design,” IAEA Safety Standards Series NS-R-1, International Atomic Energy Agency (2000); https://www-pub.iaea.org/MTCD/publications/PDF/Pub1099_scr.pdf (current as of Feb. 12, 2021).
   Google Scholar
• Y. A. KURAKOV et al., “Improvement of Operational Performance and Increase of Safety of WWER-1000/V-392,” Proc. Technical Committee Mtg. Performance of Operating and Advanced Light Water Reactor Designs, Munich, Germany, October 23–25, 2000, p. 143, International Atomic Energy Agency (2001).
   Google Scholar
• M. MOHSENDOKHT, K. HADAD, and M. JABBARI, “Reducing the Loss of Offsite Power Contribution in the Core Damage Frequency of a VVER-1000 Reactor by Extending the House Load Operation Period,” Ann. Nucl. Energy, 116, 303 (2018); https://doi.org/https://doi.org/10.1016/j.anucene.2018.01.030.
   Web of Science ®Google Scholar
• E. BORISOV, D. GRIGOROV, and K. MANCHEVA, “Study of Long-Term Loss of All AC Power Supply Sources for VVER-1000/V320 in Connection with Application of New Engineering Safety Features for SAMG,” Ann. Nucl. Energy, 59, 204 (2013); https://doi.org/https://doi.org/10.1016/j.anucene.2013.04.007.
   Web of Science ®Google Scholar
• A. VOLKANOVSKI and A. PROŠEK, “Extension of Station Blackout Coping Capability and Implications on Nuclear Safety,” Nucl. Eng. Des., 255, 16 (2013); https://doi.org/https://doi.org/10.1016/j.nucengdes.2012.09.031.
   Web of Science ®Google Scholar
• M. JABBARI, K. HADAD, and A. PIROUZMAND, “Re-Assessment of Station Blackout Accident in VVER-1000 NPP with Additional Measures Following Fukushima Accident Using Relap/Mod3.2,” Ann. Nucl. Energy, 129, 316 (2019); https://doi.org/https://doi.org/10.1016/j.anucene.2019.02.006.
   Web of Science ®Google Scholar
• “Assessment of Defence in Depth for Nuclear Power Plants,” Safety Reports Series No. 46, International Atomic Energy Agency (2005); https://www.iaea.org/publications/7099/assessment-of-defence-in-depth-for-nuclear-power-plants (current as of Feb. 12, 2021).
   Google Scholar
• M. P. PAVLOVA et al., “RELAP5/MOD3.2 Sensitivity Calculations of Loss-of-Feed Water (LOFW) Transient at Unit 6 of Kozloduy NPP,” Nucl. Eng. Des., 236, 3, 322 (2006); https://doi.org/https://doi.org/10.1016/j.nucengdes.2005.08.009.
   Web of Science ®Google Scholar
• P. VRYASHKOVA, M. ANDREEVA, and P. GROUDEV, “Study of the VVER-1000 Behaviour During LBLOCA with ID 850 mm Combined with Station Blackout Using Computer Code MELCOR 2.1,” Trans. Bulgarian Nucl. Soc., 20, 2, 110 (2015).
   Google Scholar
• B. CHATTERJEE et al., “Analyses for VVER-1000/320 Reactor for Spectrum of Break Sizes Along with SBO,” Ann. Nucl. Energy, 37, 3, 359 (2010);.
   Web of Science ®Google Scholar
• B. CHATTERJEE et al., “Severe Accident Management Strategy Verification for VVER-1000 (V320) Reactor,” Nucl. Eng. Des., 241, 9, 3977 (2011); https://doi.org/https://doi.org/10.1016/j.nucengdes.2011.06.047.
   Web of Science ®Google Scholar
• P. GROUDEV et al., “ASTEC Investigations of Severe Core Damage Behaviour of VVER-1000 in Case of Loss of Coolant Accident Along with Station-Black-Out,” Nucl. Eng. Des., 272, 237 (2014); https://doi.org/https://doi.org/10.1016/j.nucengdes.2013.06.039.
   Web of Science ®Google Scholar
• P. GROUDEV, A. STEFANOVA, and R. GENCHEVA, “Assessment of VVER 1000 Core Degradation for Bounding Cases with ASTEC 2.1.1.0,” Nucl. Eng. Des., 351, 80 (2019); https://doi.org/https://doi.org/10.1016/j.nucengdes.2019.05.020.
   Web of Science ®Google Scholar
• P. GROUDEV, A. STEFANOVA, and R. GENCHEVA, “Application of ASTEC Computer Code for Validation of SAMG Based on LB LOCA Scenario for VVER 1000,” Trans. Bulgarian Nucl. Soc., 22, 1, 13 (2017).
   Google Scholar
• M. S. DWIDDAR et al., “From VVER-1000 to VVER-1200: Investigation of the Effect of the Changes in Core,” 2; https://www.academia.edu/28063054/From_VVER_1000_to_VVER_1200_Investigation_of_the_Effect_of_the_Changes_in_Core (current as of Feb. 12, 2021).
   Google Scholar
• J. VOJACKOVA, F. NOVOTNY, and K. KATOVSKY, “Safety Analyses of Reactor VVER 1000,” Energy Procedia, 127, 352 (2017); https://doi.org/https://doi.org/10.1016/j.egypro.2017.08.079.
   Google Scholar
• “ Status Report 93 - VVER–1000 (V-466B) (VVER–1000 (V-466B)),” International Atomic Energy Agency Advanced Reactors Information System (2011); https://aris.iaea.org/sites/.%5CPDF%5CVVER-1000(V-466B).pdf (current as of Feb. 12, 2021).
   Google Scholar
• A. PIROUZMAND, A. GHASEMI, and F. FAGHIHI, “Safety Analysis of LBLOCA in BDBA Scenarios for the Bushehr’s VVER-1000 Nuclear Power Plant,” Prog. Nucl. Energy, 88, 231 (2016); https://doi.org/https://doi.org/10.1016/j.pnucene.2016.01.004.
   Web of Science ®Google Scholar
• Z. TABADAR et al., “Thermal-Hydraulic Analysis of VVER-1000 Residual Heat Removal System Using RELAP5 Code, An Evaluation at the Boundary of Reactor Repair Mode,” Alexandria Eng. J., 57, 3, 1249 (2018); https://doi.org/https://doi.org/10.1016/j.aej.2017.03.044.
   Web of Science ®Google Scholar
• B. GJORGIEV, A. VOLKANOVSKI, and G. SANSAVINI, “Improving Nuclear Power Plant Safety Through Independent Water Storage Systems,” Nucl. Eng. Des., 323, 8 (2017); https://doi.org/https://doi.org/10.1016/j.nucengdes.2017.07.039.
   Web of Science ®Google Scholar
• 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,” Prog. Nucl. Energy, 119, 103145 (2020); https://doi.org/https://doi.org/10.1016/j.pnucene.2019.103145.
   Web of Science ®Google Scholar
• P. LOBNER, “Definition of Baseline VVER-1000, V320 Systems and Evaluation of Plant Response to Postulated Accidents” (Nov. 2015); https://doi.org/https://doi.org/10.13140/RG.2.1.3920.0724.
   Google Scholar
• S. B. RYZHOV, “VVER-Type Reactors of Russian Design,” Handbook of Nuclear Engineering, p. 2249, Springer (2010); https://doi.org/https://doi.org/10.1007/978-0-387-98149-9_20.
   Google Scholar
• C. M. ALLISON and J. K. HOHORST, “Role of RELAP/SCDAPSIM in Nuclear Safety,” Innovative Systems Software (2008).
   Google Scholar
• E. YOUSIF et al., “Simulation and Analysis of Small Break LOCA for AP1000 Using RELAP5-MV and Its Comparison with NOTRUMP Code,” Sci. Technol. Nucl. Install., 2017, 1 (2017); https://doi.org/https://doi.org/10.1155/2017/4762709.
   Web of Science ®Google Scholar
• A. TRIVEDI, “Application of RELAP/SCDAPSIM for Severe Accident and Safety Analysis of Nuclear Reactor Systems,” Thesis, Indian Institute of Technology Kanpur (June 2017).
   Google Scholar
• “Best Estimate Safety Analysis for Nuclear Power Plants: Uncertainty Evaluation,” Safety Reports Series 52, International Atomic Energy Agency (2008); https://www.iaea.org/publications/7768/best-estimate-safety-analysis-for-nuclear-power-plants-uncertainty-evaluation (current as of Feb. 12, 2021).
   Google Scholar
• 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,” Prog. Nucl. Energy, 119, 103145 (2020); https://doi.org/https://doi.org/10.1016/j.pnucene.2019.103145.
   Web of Science ®Google Scholar
• A. BUCALOSSI and A. PETRUZZI, “Role of Best Estimate Plus Uncertainty Methods in Major Nuclear Power Plant Modifications,” J. Nucl. Sci. Technol., 47, 8, 671 (2010); https://doi.org/https://doi.org/10.1080/18811248.2010.9711643.
   Web of Science ®Google Scholar
• P. HERALECKY, “ Post-Test Analysis of Upper Plenum 11% Break at PSB-VVER Facility Using TRACE V5.0 and RELAP5/MOD3.3 Code,” International Agreement Report, U.S. Nuclear Regulatory Commission (May 2014).
   Google Scholar
• P. LOBNER, “Definition of Baseline VVER-1000, V320 Systems and Evaluation of Plant Response to Postulated Accidents,” Technical Report, (1987); https://doi.org/https://doi.org/10.13140/RG.2.1.3920.0724.
   Google Scholar
• D. SUN et al., “An Improved Best Estimate Plus Uncertainty Method for Small-Break Loss-of-Coolant Accident in Pressurized Water Reactor,” Front. Energy Res., 8, 1 (Aug. 2020); https://doi.org/https://doi.org/10.3389/fenrg.2020.00188.
   Web of Science ®Google Scholar