الفهرس 
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Abstract
Nuclear research reactors play an important role in supporting the nuclear energy program for most countries. Research are categorized according to the type of fuel, fuel type of moderator and reflector, the power of the and its application. Most reactors initially operated power then an era began to up-rate the power by the fuel type, improving the thermal-hydraulic system and modifying the control system to comply with new trends in research reactors and its applications. In thesis, first W8 carried out static calculation for the research reactor ETRR-1 to evaluate its power possibility. Firstly, we carried out cell calculation WIMSD/4 code to study the variation of the infinite factor with the variation of fuel enrichment, pitch and adding heavy water by increasing percentage the ordinary water coolant. These calculations are for both rod type fuel elements and plate type fuel From these calculations, we got the optimum infinite factor for a number of cases.
Secondly we carried out the over-whole core calculations CITVAP code and HXS code as an interface code between calculation code and core calculation code. We calculated the neutron flux distribution, the total reactivity and for the aforementioned cases at three power levels (2, 5, 10 MWt).
A second goal of the study is to investigate the possibility upgrading the reactor by changing the fuel type. As a plate fuel element can be manufactured locally, we carried out parametric study to show the possibility of using such a We concluded this study that the upgrading of the ETRR-l power is possible either by raising the enrichment of rod type fuel to 40% or using the plate type fuel element increasing the uranium contents of the fuel to approximately double its present value.