[en] The FRAP-T6 code was extended to calculate: (1) fuel surface azimuthal temperature distribution; (2) work done on cladding by internal pressure; and (3) azimuthal heat conduction in the cladding. The extensions were assessed by comparing calculated and measured cladding ballooning characteristics for four in-pile fuel rod tests. The assessment showed that the calculation of the fuel surface azimuthal temperature distribution improved the calculations of cladding ballooning. Both calculations and experimental results indicate that coplanar blockage due to cladding ballooning is unlikely during a large break LOCA

[en] Sealed sources are usually in capsules made of stainless steel. They are the size of a pen or a finger and contain one of hundreds of radioactive elements (e.g., Iridium, Radium) or their isotopes. They are air-tight and very durable, contain the radioactive material but not radiation. They are used in the health sector, industry, military, and universities. Incidents occurred in Met Halfa, Egypt, 2000 (Iridium-192); Goiania, Brazil, 1987 (Cesium-137); Mexico and Southwest U.S., 1977 -1984 (Cobalt-60); Peru, 1999 (Iridium-1992); Poland 2001 (Cobalt-60). The IMPRSS Mission is based on a joined partnership between the Egyptian Atomic Energy Authority, the Egyptian Ministry of Health, the Sandia National Laboratories, the International Atomic Energy Agency and others. The IMPRSS Mission protects human health and the environment in Egypt from mismanaged sealed sources, is developed jointly with MOH and EAEA, provides capabilities for managing radioactive sealed sources in Egypt, increases public awareness, provides education and training, improves emergency response capabilities, develops a permanent disposal facility, ensures the program is self-sustaining and ensures close coordination with the IAEA. Infrastructure how to manage sealed sources is discussed. It includes awareness, tracking and inventory control, security, recovery, conditioning and storage, recycling and disposal. Emergency response, regulatory reform, education and training and its targets are provided. The government of Egypt can protect the people of Egypt and is ready for emergencies. Prevention is the first line of defence and detection is the second line of defence. Adequate Emergency Response saves lives and adequate control reduces risk of mismanaged uses or deliberate misuses of sources. A Cradle-to-Grave approach is built on existing capabilities at EAEA and MOH

[en] A main objective of this work was to identify the safety requirements in the area of fuel system design and performance from both the International Atomic Energy Agency (IAEA) and U.S. Nuclear Regulatory Commission (NRC) points of view. The study covered requirements during normal plant operation as well as during accident conditions. This study revealed that, although none of the factors to be considered for fuel safety were neglected in the IAEA regulatory documents, these documents are not complete in themselves, particularly because they lack quantitative guidelines and specific industrial standards. Although generality makes the IAEA requirements adaptable to many countries, on the other hand, it makes their applicability constrained by the availability of highly qualified and experienced personnel who can translate the qualitative requirements given in these documents into actual engineering solutions. 20 refs

[en] Naturally Occurring Radioactive Material (NORM) contains radium and thorium and such materials arise from the petroleum extraction industries. The safe handling of these NORM in Egypt implies identification of the responsibilities of both the producer of the NORM and the Central Radioactive Management Authority. In Egypt, this authority is the Hot Laboratory and Waste Management Centre (HLWMC). In the regulations NORM is classified into categories 1 and 2 according to their radiation level. The responsibilities of the producer include waste collection, packaging of category 1 and interim storage of category 2. The responsibilities of the HLWMC include transportation and long term storage of category 1. The responsibilities of the Regulatory Body and the licensing conditions are identified. (author)

[en] The radioactive materials in ''public'' locations are typically contained in small, stainless steel capsules known as sealed radiation sources (RS). These capsules seal in the radioactive materials, but not the radiation, because it is the radiation that is needed for a wide variety of applications at hospitals, medical clinics, manufacturing plants, universities, construction sites, and other facilities in the public sector. Radiation sources are readily available, and worldwide there are hundreds of thousands of RS. The IMPRSS Project is a cooperative development between the Egyptian Atomic Energy Authority (EAEA), Egyptian Ministry of Health (MOH), Sandia National Laboratories (SNL), New Mexico Tech University (NMT), and Agriculture Cooperative Development International (ACDI/VOCA). SNL will coordinate the work scope between the participant organizations

[en] The situation of the radiation sources in Egypt is elucidated. The inventory of the sources is being completed to implement a national date base. Compliance with the IAEA code of conduct is being implemented. Security measures are being evaluated (author)

[en] The preparation of L-thyroxine labelled with ⁵⁷cobalt for use as a second tracer in dual radioimmunoassay techniques for different biological molecules is described. The labelling procedure was monitored by paper chromatography and polyacrylamide gel electrophoresis; a yield of 42±10% (mean ±1 SD) was achieved in a total of 39 conjugation reactions. The method was optimized in terms of pH, reaction completion time, reactant concentration, and solubility of the tracer. A radioimmunoassay for thyroxine in human serum was developed utilizing this tracer, and this compared favorably with an established technique in which ¹²⁵iodine was used as the tracer. 16 refs.; 6 figs.; 1 table

[en] The dielectric properties of yttrium oxide-doped cerium oxide solid solutions have been studied by using a.c. techniques. Frequency and temperature respectively range from 10 to 10₅ Hz and from 70 to 200 deg C. Both a complex impedance plot (Z'' vs Z') and a conductance plot (G at fixed frequency vs inverse of temperature T^-₁) are shown to be complementary for an accurate determination of the bulk resistance and of the dielectric loss. For the three investigated concentrations of yttrium oxide (m/% YOsub(1,5):0.001, 0.01 and 0.1), the activation energies for conduction are equal to 0.86, 0.75 and 0.75 eV, while the activation energy for dipole reorientation is found to be concentration independent (0.75 eV; angular frequency preexponential factor: 6.0 x 10₁₂, 1.43 x 10₁₃ and 3.05 x 10₁₃ s^-₁). Moreover, the dipolar relaxation rates are found to be of the same order of magnitude as that of the migration rate. Interpretation is given on the basis of Wachtman's model and of previous results obtained by Nowick et al. from ITC (ionic thermo-current) investigations. The observed dielectric peak appears to be due to the redistribution of oxygen vacancies between charged (Ysub(Ce)-Vsub(O)) pairs and fixed charged Ysub(Ce) defects. (author)

[en] The present study aims to use the α-spectroscopy at Nuclear Materials Authority (NMA) of Egypt. A radiochemical technique for analysis uranium isotopes was carried out for ten mineralized granitic samples together with the International standards RGU-1 (IAEA) and St_4 (NMA). Several steps of sample preparation, radiochemical separation and source preparation were performed before analysis. Uranium was separated from sample matrix with 0.2 M TOPO in cyclohexane as an extracting agent with a chemical yield 98.95% then uranium was purified from lanthanides and actinides present with 0.2 M TOA in xylene as an extracting agent. The pure fraction was electrodeposited on a mirror-polished copper disc from buffer solution (NaHSO_4+H_2SO_4+NH_4OH). Rectangle pt-electrode with an anode-cathode distance of 2 cm was used. Current was 900 mA and the electrodeposition time reach up to 120 min. The achieved results show that the chemical yield ranged between 87.9±6.8 and 98±8.6. - Highlights: • Radiochemical technique for analysis uranium isotopes. • Alpha-particle spectrometry is performed after a radiochemical procedure. • Electrodeposition conditions for preparation of alpha uranium source. • Using "2"3"2U (t_1_/_2=70.6a, E_α=5320.24 keV, intensity=69.1%) as an internal tracer makes it a highly reliable technique

[en] Ilmenite was added to Ordinary Portland Cement to Modify the characteristic properties of the matrix as density, compressive strength and thermal stability . Coal tar and radiocesium were solidified as hazardous waste in cement-ilmenite matrix. The physical properties as density, sitting times and porosity were studied. The mechanical properties as compressive strength values and the chemical properties as leaching were measured