Investigation of the Capability of REALP5 to Solve Complex Fuel Geometry

Authors: D. Abdelrazek, M. NaguibAly, A. A. Badawi, Asmaa G. Abo Elnour, A. A. El-Kafas

Abstract:

This work is developed within IAEA Coordinated Research Program 1496, “Innovative methods in research reactor analysis: Benchmark against experimental data on neutronics and thermal-hydraulic computational methods and tools for operation and safety analysis of research reactors”.

The study investigates the capability of Code RELAP5/Mod3.4 to solve complex geometry complexity. Its results are compared to the results of PARET, a common code in thermal hydraulic analysis for research reactors, belonging to MTR-PC groups.

The WWR-SM reactor at the Institute of Nuclear Physics (INP) in the Republic of Uzbekistan is simulated using both PARET and RELAP5 at steady state. Results from the two codes are compared.

REALP5 code succeeded in solving the complex fuel geometry. The PARET code needed some calculations to obtain the final result. Although the final results from the PARET are more accurate, the small differences in both results makes using RELAP5 code recommended in case of complex fuel assemblies. 

Keywords: Complex fuel geometry, PARET, RELAP5, WWR-SM reactor.

Digital Object Identifier (DOI): doi.org/10.5281/zenodo.1091486

References:

[1] Antonella L. Costa, Patricia Amelia L.Reis, et al. "Thermal Hydraulic Analysis of the IPR-R1 TRIGA Research Reactor Using a RELAP5 Model”, Nuclear Engineering and design 240, pp 1487-1494, 2010.
[2] INVAP,” Replacement Research Reactor Project- SAR-Ch 16- Safety Analysis”, Australian Nuclear Science and Technology Organization, November 2004.
[3] P.L. Garner and N.A. Hanan, "Transient Analyses for the Uzbekistan WWR-SM Reactor with IRT-3M HEU Fuel and IRT-4M LEU Fuel”, Nuclear Engineering Division, Argonne National Laboratory, August 2007.
[4] IAEA, Proceeding Series on "Innovative Methods in Research Reactor Analysis: Benchmark against Experimental Data on Neutronics and Thermal Hydraulic Computational Methods and Tools for Operation and Safety Analysis of Research Reactors”, Vienna (2010).
[5] IAEA-TECDOC 233, "Research Reactor Core Conversion from the Use of Highly Enriched Uranium to the Use of Low Enriched Uranium Fuels”, 1980.
[6] John E. Edwards, "Design and Rating Shell and Tube Heat Exchangers”, P & I Design Ltd, Teesside, UK, Issued 29 August 08.
[7] Green, Don W.; Perry, Robert H., "Perry's Chemical Engineers' Handbook”, 8th ed., McGraw-Hill, December 2008.