Effect of regulation valves (RV) installation in high pressure injection system (HPIS) pipelines on the formation of reactor pressure vessel (RPV) thermal stress conditions was analyzed. Modernization is implemented at South-Ukrainian nuclear power plant (SUNPP) Unit 1 within the framework of life extension, which finished by the end of 2013. The main goal of the modernization is to expand the HPIS functionality for small leak accident and protection against the cold overpressurization due to flow rate and primary pressure effectively regulation. The thermal hydraulic model for RELAP5/mod3.2 code with detailed downcomer (DC) model and changes in accordance with modernization was used for calculations. Detailed (realistic) modeling of piping and equipment was performed. Also, an algorithm for the RVs was developed. Applying of cooling water flow rate regulation avoids excessive primary cooling and, consequently, helps to preserve the RPV integrity and to prevent reaching through crack formation, which can lead to a severe accident.
Skip Nav Destination
2014 22nd International Conference on Nuclear Engineering
July 7–11, 2014
Prague, Czech Republic
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4590-5
PROCEEDINGS PAPER
Effect of Regulation Valves Installation in High Pressure Injection System Pipelines on the Formation of Reactor Vessel Thermal Stress Conditions
Aleksander Mazurok,
Aleksander Mazurok
ENERGORISK, Ltd., Kyiv, Ukraine
Search for other works by this author on:
Maksym Vyshemirskyi
Maksym Vyshemirskyi
ATOMENERGOSERVICE, Ltd., Kyiv, Ukraine
Search for other works by this author on:
Aleksander Mazurok
ENERGORISK, Ltd., Kyiv, Ukraine
Maksym Vyshemirskyi
ATOMENERGOSERVICE, Ltd., Kyiv, Ukraine
Paper No:
ICONE22-30437, V02AT09A055; 10 pages
Published Online:
November 17, 2014
Citation
Mazurok, A, & Vyshemirskyi, M. "Effect of Regulation Valves Installation in High Pressure Injection System Pipelines on the Formation of Reactor Vessel Thermal Stress Conditions." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 2A: Thermal Hydraulics. Prague, Czech Republic. July 7–11, 2014. V02AT09A055. ASME. https://doi.org/10.1115/ICONE22-30437
Download citation file:
7
Views
Related Proceedings Papers
Related Articles
Analyses of Feedwater Trip With SBO Sequence of VVER1000 Reactor
ASME J of Nuclear Rad Sci (October,2016)
The Application of System CFD to the Design and Optimization of High-Temperature Gas-Cooled Nuclear Power Plants
J. Eng. Gas Turbines Power (May,2008)
External Hazard Coinciding With Small Break LOCA—Thermohydraulic Calculation With System Code ATHLET
ASME J of Nuclear Rad Sci (April,2020)
Related Chapters
PSA Level 2 — NPP Ringhals 2 (PSAM-0156)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Iwe and Iwl
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 2, Third Edition
IWE and IWL
Companion Guide to the ASME Boiler & Pressure Vessel Code, Volume 2, Second Edition: Criteria and Commentary on Select Aspects of the Boiler & Pressure Vessel and Piping Codes