THERMAL SCIENCE

International Scientific Journal

A RELAP5 MODEL FOR THE THERMAL-HYDRAULIC ANALYSIS OF A TYPICAL PRESSURIZED WATER REACTOR

ABSTRACT
This study describes a RELAP5 computer code for thermal-hydraulic analysis of a typical pressurized water reactor. RELAP5 is used to calculate the thermal hydraulic characteristics of the reactor core and the primary loop under steady-state and hypothetical accidents conditions. New designs of nuclear power plants are directed to increase safety by many methods like reducing the dependence on active parts (such as safety pumps, fans, and diesel generators ) and replacing them with passive features (such as gravity draining of cooling water from tanks, and natural circulation of water and air). In this work, high and medium pressure injection pumps are replaced by passive injection components. Different break sizes in cold leg pipe are simulated to analyze to what degree the plant is safe (without any operator action) by using only these passive components. Also station blackout accident is simulated and the time response of operator action has been discussed.
KEYWORDS
PAPER SUBMITTED: 2008-10-24
PAPER REVISED: 2009-02-24
PAPER ACCEPTED: 2009-06-13
DOI REFERENCE: https://doi.org/10.2298/TSCI1001079A
CITATION EXPORT: view in browser or download as text file
THERMAL SCIENCE YEAR 2010, VOLUME 14, ISSUE Issue 1, PAGES [79 - 88]
REFERENCES
  1. Schulz, T. L., Westinghouse AP1000 Advanced Passive Plant, Nuclear Engineering and Design, 236 (2006), 14-16, pp. 1547-1557
  2. Cummins, W. E., Corletti, M. M., Schulz, T. L., Westinghouse AP1000 Advanced Passive Plant, Proceedings, ICAPP, Cordoba, Spain, 2003, www.ukap1000application.com">www.ukap1000application.com">www.ukap1000application.com
  3. ***, RELAP5/MOD3 Code Manual, 1995. NUREG/CR-5535, INEL-95/0174
  4. Woods, B. G., Nelson, R. K., Reyes, J. N., Behavior of Core Make-up Tanks, Proceedings, 4th Research Coordination Meeting of the IAEA CRP on Natural Circulation Phenomena, Modeling and Reliability of Passive Systems that Utilize Natural Circulation, Vienna, 2007
  5. Banerjee, S., et al., Scaling in the Safety of Next Generation Reactors, Nuclear Engineering and Design 186 (1998), 1-2, pp. 111-133
  6. Achilli, A., et al., Two New Passive Safety Systems for LWR Applications, Nuclear Engineering and Design, 200 (2000), 3, pp. 383-396
  7. Bruce, R. A., A Safe, Simplified PWR and its Environment, Proceedings, 24th Intersociety IEEE Energy Conversion Engineering Conference, Washington DC, USA, 1989, Vol. 5, pp. 2425-2429
  8. Robbe, M., Lepareux, M., Trollat, C., Hydrodynamic Loads on a PWR Primary Circuit Due to a LOCA, Nuclear Engineering and Design, 211 (2002), 2-3, pp. 189-228
  9. Kwon, Y. M., Lim, H. S., Song, J. H., Design Options for Safety Depressurization System, Nuclear Engineering and Design, 179 (1997), 3, pp. 287-296
  10. Bodansky, D., Nuclear Energy, Principles, Practices, and Prospects, 2nd ed., AIP Press, Washing ton, USA, 2004
  11. Petrangeli, G., Nuclear Safety, Elsevier, UK, 2006
  12. Kun, Z., Wu-Xue, C., Ji-Yao, C., Study on Severe Accident Mitigation Measures for the Development of PWR SAMG, Nuclear Science and Techniques, 17 (2006), 4, pp. 245-251
  13. Reventos, F., et al., Analysis of the Feed & Bleed Procedure for the Asco NPP: First Approach Study for Operation Support, Nuclear Engineering and Design, 237 (2007), pp. 2006-2013

© 2022 Society of Thermal Engineers of Serbia. Published by the Vinča Institute of Nuclear Sciences, National Institute of the Republic of Serbia, Belgrade, Serbia. This article is an open access article distributed under the terms and conditions of the Creative Commons Attribution-NonCommercial-NoDerivs 4.0 International licence