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
The present work is concerned on neutron flux increasing in Tehran Research Reactor (TRR). TRR is a 5 MW pool-type research reactor with plate type fuels in which the light water is used as both the coolant and moderator. The main goal of this paper is reaching to the average thermal neutron flux of the order of 1014 #/cm-2.s-1 in the central irradiation box. Combination of the TRR power upgrading with the compact core can enable us to reach a neutron flux higher than 1.5 × 1014 #/cm-2.s-1 without violating the neutronic and thermal-hydraulic safety criteria. The compact core, with 19 and 5 standard and control fuel elements respectively, is used as a base for the neutronic analyses. Compact core with 26 fuel assemblies fulfilled all neutronic and operation criteria. Considering thermal hydraulic aspect from previous study lets TRR to be upgraded to 8.5 MW, resulting in neutron thermal flux greater than 1.5 × 1014
Highlights
- The main goal is reaching to the average thermal neutron flux of the order of 1.5 × 1014 #/cm-2.s-1.
- Combining the TRR power upgrading with the compact core configuration is the main idea of this study.
- The results showed that TRR can be upgraded to 8.5 MW and the thermal flux larger than 1.5 × 1014 can be achievable.
Keywords
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