[en] Refractory metal silcides are under intensive investigation to be used as contact and interconnect materials in VLSI circuits. Ion beam mixing has been proposed as a technique for simultaneous doping and metal silicide formation. This work presents a theoretical model for calculating the different parameters required for ion beam mixing through ion implantation. The minimum ion beam energy and dose for complete mixing is calculated. A plot of the obtained energy-dose relation shows that the dose increases linearly with energy. The dose-silicide thickness relation is also plotted. It is found that the thickness of the formed metal silicide increases linearly with the square root of the applied dose. A good agreement is found between the values and relations of the proposed model and experimental results. (orig.)

[en] The uncertainty in the nuclear data in the actinide region should be as small as possible because they are the basis behind all simulations of nuclear reactor core behavior over both long time scale (fuel depletion and waste production) and short time scale (accident scenarios). Large model prediction uncertainties increase design margins, which in turn, increase fuel cycle cost and limit the plant's power rating. With the core attributes uncertainties understood, optimization upon current design margins could be utilized. In this paper, a model for very high temperature reactor (VHTR) is developed using Monte Carlo code. The model is used to predict the uncertainty that originates in the reactor parameters due to the uncertainties in reaction cross sections of (U²³⁵ - C). The effect of the uncertainty in the nuclear cross sections is shown for the neutron flux. The flux was found to change linearly with the uncertainty in the fission cross section in the thermal region. Changes in the scattering cross section of carbon also can have significant effect on the flux in the fast, intermediate and thermal regions. (authors)

[en] The 3D temperature distribution in the First Wall (FW) of the International Thermonuclear Experimental Reactor (ITER) blanket is studied. The effect of FW exposure to different heat fluxes and heat generation rates on the temperature distribution inside the wall is also examined. The design of FW adopted by ITER council in 2001 is taken as a reference design for the FW through the analysis. The study reveals that the maximum and minimum temperatures increase linearly along the poloidal direction according to the specified incident heat flux and heat generation. The study also indicates a linear variation for the coolant temperature along the cooling channels throughout the poloidal direction

[en] Collaboration of universities and academics with the regulatory body, the operator and other stakeholders to enhance nuclear security is mandatory for success of efforts and activities of nuclear security. For newcomer countries, training in the field of nuclear security focuses mainly on providing the basic training requirements and on enhancing the nuclear security culture. The availability of qualified specialists in the field nuclear security is essential for the establishment of a nuclear security regime in different countries. Unlike operating nuclear power countries, nuclear power newcomers have a limited pool of nuclear security experts. Those experts are needed in industry, regulatory body, educational institutions and training centers. Therefore, an HRD action plan should be developed and implemented to ensure future sustainability. A significant part of the HRD plan can be provided via universities with experience in safety and security. Such universities can provide education and training for current and future workforce and improve nuclear security tools, properties and characteristics through research. In Egypt, there are two universities currently working on nuclear security education and training; and can be considered as a role model for collaboration between academia and nuclear regulator and operator in the context of nuclear security; Alexandria University and Suez Canal University. Both universities have established two memorandum of understanding with the ENRRA for cooperation in nuclear security education and training. Both universities are also active participants in INSEN (International Nuclear Security Education Network). This paper discusses the collaboration between Alexandria University and Suez Canal University with the Egyptian Nuclear and Radiological Regulatory Authority (ENRRA) and the role they play in nuclear security education; via providing programmes, courses and modules, training through programmes and workshops and graduate research (Mater and Ph.D. levels). (author)

[en] Highlights: • The RSG-GAS reactor was simulated using RELAP5/Mod3.4. • The credibility of RELAP5 code to predict the research reactor behavior was studied. • The code results are compared with experimental results in steady state and transient. • It showed a good agreement in steady state and most points of transient. • The deviation due to that the initial conditions of pool were not provided. - Abstract: The present work is developed within the frame of the IAEA Coordinated Research Program 1496, “Innovative methods in research reactor analysis: Benchmark against experimental data on neutronics and thermal-hydraulic computational methods and tools for operation and safety analysis of research reactors”. The objective of this work is to test the credibility of RELAP5 code in simulating the research reactor behavior during transients. Where, the code’s results were compared to the experimental measurements taken from Instrumented (thermocouple) Fuel Elements (IFE), installed at several positions in the core. The research reactor used in this study is the RSG-GAS reactor, located in the Serpong in Indonesia. Both the steady state and the transient simulation results performed using RELAP5 code for, are presented in this work. The calculated values for the coolant and clad surface temperature, at different locations in the core, showed an agreement with the experimental values with a difference less than 7% for the steady state, and with a difference less than 10% for transient conditions. However, RELAP5 was unable to predict the measured value of the coolant output temperature after the natural convection begins especially after stagnation occurred. In this case, the difference between the code results and experimental data was about 23%

[en] As a part of the Egyptian human resource development programme in nuclear security, the Department of Nuclear and Radiation Engineering in Alexandria University (the Department), as one of the oldest departments in the nuclear field in the Middle East and Africa, plays a significant role in enhancing nuclear security education and spreading nuclear security culture in the country. It was established in 1963 as a part of the Egyptian Nuclear Program at that time. The activities of the Department can be divided among three main themes: — Education and training — Research, and, — Services towards community, whether national, regional or international. Currently, the Department has recognized the need for human resource development in nuclear security education. The availability of qualified specialists in all areas of nuclear security is essential for the establishment of a nuclear security regime in different countries. Therefore, a number of activities were done and planned in the Department to respond to those needs. This paper discusses the current status and future plans of the nuclear security, as undertaken and foreseen by the Department of Nuclear and Radiation Engineering. (author)

[en] One of the significant factors of neutron radiographic image degradation is scattering blur from the object. A practical method is described to enhance image quality by eliminating the overlapping of scattered thermal neutrons component from the objects in ETRR-2 neutron radiography facility, using aluminum Gd-coated antiscatter grid. The MCNP code was used to determine the optimum grid dimensions that will reduce the scattered thermal neutrons from the object. An experiment was performed to determine the optimum grid height and irradiation time that gives the best image with acceptable geometric unsharpness. Using the MCNP code it was found that 97% of the scattered neutrons were removed by the grid. The wall dimensions and Gd coating are so small that the facility resolution cannot detect the image pattern superposition on the film

[en] The purpose of the this study was to measure the entrance surface air kerma (ESAK) and body organs, and the effective doses in intravenous urography (IVU) X-ray examinations in Sudanese hospitals. Seventy-two patients who underwent IVU multiple radiographs from five hospitals (six rooms) were examined. ESAK was calculated from incident air kerma (Ki) using patient exposure parameters and tube output Y(d). Dose calculations were performed using CALDOSE X 5.1 Monte Carlo-based software. Risk of cancer induction (4–8) and mortality per million (2–4) varied. The gallbladder, colon, stomach, gonads and uterus received organ doses of 5.3, 3.6, 3.2, 0.61, and 0.8 mGy, respectively. ESAK values ranged from 6.6 to 15.3 mGy (effective doses: 0.70–1.6 mSv). Mean ESAK fall slightly above the diagnostic reference level. Several optimization strategies to improve dose performance were discussed. Reducing the number of radiographs and the use of technique charts according to patient sizes and anatomic areas are among the most important dose optimization tools in IVU. - Highlights: • ESAK values were 6.6–15.3 mGy, while cancer induction (4–8) and mortality per million (2–4) varied. • Reducing radiographs and technique charts are important dose optimization tools. • Digital techniques improve diagnostic quality and have low costs and complications