Neutronic design of new rod type control fuel element with 3-5% enrichment in Tehran research reactor

Document Type : Research Paper

Authors

1 Ph.D. Student, School of Mechanical Engineering, Shiraz University, Shiraz, Iran

2 Professor, Nuclear Science and Technology Research Institute, AEOI, Tehran, Tehran, Iran

3 Assistant Professor, Nuclear Science and Technology Research Institute, AEOI, Tehran, Tehran, Iran

Abstract

The purpose of this research is feasibility study of irradiating the rod type control fuel element consists of UO2 fuel rods with 3-5% enrichment in Tehran research reactor with respect to neutronic criteria. Rod type control fuel assembly has 12 fuel rods with 1.36 cm outer diameter arranged in a 3 by 4 lattice with 1.633cm pitch. In order to perform reactivity worth analysis, loading of the rod type fuel with 3-5% of enrichment in TRR reference core have been studied and possibility of loading rod type fuel assembly in TRR core is investigated from the neutronic viewpoint. Then for safety analysis and evaluation of the under moderated conditions, calculation of optimum pitch and radius of rod fuels with 3-5% enrichment have been performed and finally rod type control fuel assembly with 3.34% enrichment have been chosen as fuel, . Loading this fuel in three arrangement of TRR core has been studied from the neutronic viewpoint. Results show that by loading the rod type control fuel assembly in the TRR core, all operating conditions from the neutronic viewpoint are satisfied and irradiation test will not induce any reduction of the reactor safety.

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