Hussein Gamal, Aly Shaaban, Mohamed Abdulhameed, Ashrakat Helal, Menna Mohamed, and Ayah Elshahat*

Nuclear and Radiation Engineering Department, Faculty of Engineering, Alexandria University, Egypt

*Corresponding Author: Ayah Elshahat, Nuclear and Radiation Engineering Department, Faculty of Engineering, Alexandria University, Egypt.

Received: May 13, 2022; Published: July 29, 2022

Abstract

System codes have always been used to ensure the safety of nuclear reactors in both transient and accident conditions. This paper uses RELAP-SCDAPSIM to perform a safety analysis of VVER-1000 during a reactor coolant pump (RPC) trip in the absence of the Reactor Power Limitation Controller (RPLC). Based on the single-failure criterion, The malfunction of RPLC activates the Reactor Power Controller (RPC) causing scram. Thermal imbalance and flow reversal are the most characteristic consequences of RCP trip. The interplay of these two phenomena in the existence of scram is thoroughly examined, and the effect on reactor parameters is discussed. It has been found that a new steady state is established within 400 seconds of transient initiation, and all the acceptance criteria have been fulfilled. It can be concluded that although scram is not normally effected in response to an RCP trip, VVER-1000 can safely respond to this transient in the absence of the RPLC, and maintain a steady state without any operator intervention for at least three hours.

Keywords: VVER-1000; Pump Trip; Scram; RELAP-SCDAPSIM; Safety Analysis

References

1. International Atomic Energy Agency. “Accident Analysis for Nuclear Power Plants with Pressurized Water Reactors”. Safety Reports 30 (2003): 65.
2. Y Rahmani. “Safety analysis of vver-1000 type reactors against pump failure accident in 2 and 4 loops”. The 7^th International Scientific and Technical Conference “Safety Assurance of NPP with VVER” (2011).
3. Innovative Systems Software, The KNPP VVER-1000 Sample Model.
4. “The VVER Today”. Technical Report.
5. International Atomic Energy Agency. “Status report 107: VVER-1200 (V-392M)”. 1200 (2011).
6. P Grudev and M Pavlova. “Simulation of loss-of-flow transient in a VVER-1000 nuclear power plant with RELAP5/MOD3.2”. Progress in Nuclear Energy1 (2004): 1-10.
7. P Groudev and A Stefanova. “Validation of RELAP5/MOD3.2 model on trip off one main coolant pump for VVER 440/V230”. Nuclear Engineering and Design12 (2006): 1275-1281.
8. MF Lozano., et al. “Assessment of a Reactor Coolant Pump Trip for TRILLO NPP with RELAP5/MOD3.2”. U. S. Nuclear Energy Commission, Technical Report (2000).
9. International Atomic Energy Agency. “IAEA Safety Glossary: 2018 Edition” (2019).
10. P Groudev and M Pavlova. “Total Loss of Feed Water for VVER 1000”. Fifth International Information Exchange Forum (2000).
11. J Kitto and S Shultz. “Steam: Its Generation and Use, 41^st ed”. Babcock and Wilcox Company (2005).

Citation

Citation: Ayah Elshahat., et al. “Analysis of the Pump Trip Transient in VVER-1000". Acta Scientific Applied Physics 2.8 (2022): 21-27.

Copyright

Copyright: © 2022 Ayah Elshahat., et al. This is an open-access article distributed under the terms of the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original author and source are credited.