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Science and Technology of Nuclear Installations
Volume 2018 (2018), Article ID 7862847, 11 pages
Research Article

Study of Fast Transient Pressure Drop in VVER-1000 Nuclear Reactor Using Acoustic Phenomenon

1Department of Nuclear Engineering, Science and Research Branch, Islamic Azad University, Tehran, Iran
2Department of Energy Engineering, Faculty of Engineering, Sharif University of Technology, Tehran, Iran

Correspondence should be addressed to Mohammad Rahgoshay

Received 10 June 2017; Revised 3 September 2017; Accepted 10 September 2017; Published 31 January 2018

Academic Editor: Eugenijus Ušpuras

Copyright © 2018 Soroush Heidari Sangestani et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.


This article aims to simulate the sudden and fast pressure drop of VVER-1000 reactor core coolant, regarding acoustic phenomenon. It is used to acquire a more accurate method in order to simulate the various accidents of reactor core. Neutronic equations should be solved concurrently by means of DRAGON 4 and DONJON 4 coupling codes. The results of the developed package are compared with WIMS/CITATION and final safety analysis report of Bushehr VVER-1000 reactor (FSAR). Afterwards, time dependent thermal-hydraulic equations are answered by employing Single Heated Channel by Sectionalized Compressible Fluid method. Then, the obtained results were validated by the same transient simulation in a pressurized water reactor core. Then, thermal-hydraulic and neutronic modules are coupled concurrently by use of producing group constants regarding the thermal feedback effect. Results were compared to the mentioned transient simulation in RELAP5 computer code, which show that mass flux drop is sensed at the end of channel in several milliseconds which causes heat flux drop too. The thermal feedback resulted in production of some perturbations in the changes of these parameters. The achieved results for this very fast pressure drop represent accurate calculations of thermoneutronic parameters fast changes.