الفهرس 
INTRODUCTIONOnly 14 pages are availabe for public view
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Abstract
The Research Reactors are designing to provides a source of neutrons and/or gamma radiations for research into applied physics, biology, or chemistry, or to assist in the investigation of the effects of radiation on any type of materials. A distinguishing feature is the incorporation of many beam holes to allow neutrons and gamma rays to leave the core. all reactors whether the research or power productions in order to provide the neutron source, they operate through fission chain reaction under controlled conditions. These operation requirements are based on the optimization of the usage of the reactor, both in fuel assemblies (FAs) and irradiation facilities. The type of research reactor (RR) that is utilizing for source of neutrons and gamma radiations, are known as open pool Australian lightwater research reactor, located in Australia Sydney. The Open Pool Australian Lightwater (OPAL) research reactor compact core consists of 4×4 low enriched uranium (LEU<19.8wt.% 235U) fuel assemblies dispersed with uranium-silicide fuels (U3Si2-Al), each comprising 21 fuel elements. The reactor core is cooled and moderated by light-water and reflected by heavy water contained in a reflector vessel and two independent shutdown systems that is first shut-down system (FSS) consisted of five hafnium control rods and second shut-down system (SSS) contained the draining of the heavy water is presented in the reflector vessel. The purpose of this study will be core neutronics calculations of the OPAL research reactor to comparison with ANSTO experimental data. Those comprise of critical positions of control rod calibrations (CRC) in cold fresh state that is consisted of three type of fuels assemblies (standard and type two fuels with burnable poison, type one fuel without burnable poison); control rod worth (CRW) calculations with the control rods position; Thermal neutron flux profile and Power distribution inside the reactor core and critical positions with burn-up (hot full power state). The performance for core neutronic and burnup calculations of the OPAL research reactor in this thesis is using the Monte Caro Neutron Particle Transport (MCNP5/MCNPX) code. the Operating state of reactor core calculations were performed in MCNP code with a 3D model of the OPAL research reactor. The 3D model is concerned merely the reactor core with overall fuel assemblies including fuel meat and cladding of the fuels, chimney and reflector vessels. The results of core neutronics and burn-up calculations were verified against ANSTO measurements data of the reactor status for fresh core and that is very good agreement with the experimental measurements data. the thermal neutron flux profile inside reactor core calculations was found 1.94×1014n/cm2 .s1 that is very good agreement compared with ANSTO measurement data and the burn-up calculations are quantified and explained comprising the effective multiplication factor (keff) trend lines. the calculated and measured critical configuration difference is below 500pcm for all cases (overall control rods). the average keff was 1.00235 in entirely control rods. the reactivity worth calculation results are closely matched within the ANSTO experimental measurement data within numerical uncertainty error roughly 3%.