A peer-reviewed journal published by K. N. Toosi University of Technology

Thermo-hydraulic feasibility study for the power-upgraded of Tehran Research Reactor compact core

Document Type : Research Article

Authors

1 Department of Physics, K.N. Toosi University of Technology, P.O. Box 15875-4416, Tehran, Iran

2 Nuclear Reactor and Safety School, Nuclear Science and Technology Research Institute (NSTRI), Atomic Energy Organization of Iran, Tehran, Iran

Abstract
This study investigates the power upgrade of the Tehran Research Reactor (TRR) to enhance neutron flux for various applications. Two strategies are proposed: (1) utilizing spent fuel for economic feasibility and (2) adopting a compact core layout to maximize neutron flux. Neutronic simulations reveal that the compact core with 26 fuel assemblies can safely operate at 8.5 MW, achieving a thermal neutron flux greater than 1.5×1014 n.cm-2·s-1. Thermal-hydraulic analysis shows that, with a power peaking factor (PPF) of 2.7, safety criteria are met at 8.5 MW. Reducing the power to 8.3 MW ensures full compliance with all safety requirements. Under a conservative approach with a PPF of 3.0, a safe operational power of 7.5 MW is achievable. Moreover, lowering the coolant inlet temperature by 3 °C improves reactor performance, allowing safe operation at 8.5 MW, with potential to exceed 9 MW at high mass flow rates while maintaining safety margins.

Highlights

  • Two upgrade strategies: reuse of spent fuel and compact core design for enhanced neutron flux.
  • Compact core with 26 fuel assemblies operates safely at 8.5 MW, achieving >1.5×1014 n.cm−2.s−1 thermal flux.
  • Thermal-hydraulic analysis confirms safety at 8.5 MW with PPF = 2.7 and full compliance at 8.3 MW.
  • Conservative analysis (PPF = 3.0) allows safe operation at 7.5 MW.
  • Lowering coolant inlet temperature by 3 °C enables safe operation at 8.5 MW and potential for >9 MW.

Keywords


 

Copyright
RPE is licensed under a Creative Commons Attribution-NonCommercial 4.0 International License (CC BY-NC 4.0).

Conflict of Interest

‎The authors declare no potential conflict of interest regarding the publication of this work‎.

Funding

‎The authors declare that no funds‎, ‎grants‎, ‎or other financial support were received during the preparation of this manuscript‎.

 

 
Abbate, P. (2003a). CAUDVAP V 3.60: a Computer Program for Flow Distribution and Pressure Drop Calculation in a MTR Type Core. INVAP SE.
Abbate, P. (2003b). TERMIC v. 4.1: a Program for the Calculus and Thermal-hydraulic Design of Research Reactor Cores.
Aminfarkhani, S. T., Lashkari, A., and Masoudi, S. F. (2023). Neutronic feasibility study for neutron flux upgrading of Tehran research reactor. Radiation Physics and Engineering, 4(4):27–34.
Arshi, S. S., Jozvaziri, A., Mirvakili, S., et al. (2021). A methodology to enhance thermal neutron flux in Tehran Research Reactor core for domestic fuel test purposes. Progress in Nuclear Energy, 136:103726.
Bradley, E. (2009). Research Reactor Modernization and Refurbishment. IAEA Progress report.
Farhadi, K. and Khakshournia, S. (2008). Feasibility study for Tehran Research Reactor power upgrading. Annals of Nuclear Energy, 35(7):1177–1184.
Gholamzadeh, Z., Khoshahval, F., Mozafari, M. A., et al. (2019). Computational investigation of Tehran research reactor graphite reflector replacement with Be, BeO or D2O and its impacts on thermal neutron flux enhancement. International Journal of Nuclear Energy Science and Technology, 13(4):350–371.
IAEA (2001). Safety Analysis Report for Tehran Research Reactor.
IAEA (2002). The Budapest Research Reactor: Past, present and future. Proceedings of the International Conference on Research Reactor Utilization, Safety and Management. Vienna.
IAEA (2014). Applications of research reactors. Vienna: International atomic energy agency.
IAEA-TECDOC-233 (1980). Research Reactor Core Conversion from the use of Highly Enriched Uranium to the use of Low Enriched Uranium. Appendix A U.S. Generic Enrichment Reduction calculations for plate type and rodded type reactors’, ANL (USA).
INVAP (2001). TRR amendment to the safety report, version B.
Israr, M., Abdullah, M., and Pervez, S. (2009). Refurbishment and power upgrade of Pakistan Research Reactor-1 (PARR-1). Modernization and Refurbishment, page 133.
Kalimullah, M., Olson, A., Feldman, E., Ozar, B., Yang, S., Yoon, D., and Licht, J. (2023). A User’s Guide to the PLTEMP/ANL Code. Technical report, Argonne National Laboratory (ANL), Argonne, IL (United States).
Sudo, Y. and Kaminaga, M. (1993). A new CHF correlation scheme proposed for vertical rectangular channels heated from both sides in nuclear research reactors.
Whittle, R. and Forgan, R. (1967). A correlation for the minima in the pressure drop versus flow-rate curves for sub-cooled water flowing in narrow heated channels. Nuclear Engineering and Design, 6(1):89–99.
 
Volume 6, Issue 4
Autumn 2025
Pages 29-37

  • Receive Date 29 April 2025
  • Revise Date 02 June 2025
  • Accept Date 14 July 2025