The method of measurement dosimetry in neutron – gamma field by using CaSo4 : Dy (PTFE) disc which has a diameter of 1.3mm and thickness of 0.2mm and using hydrogenated material as a converters of neutron to recoil protons (n-p) reaction, the discs were irradiated by neutron source (241Am-Be) with flux of 4.5?105 n/cm2s for different time to obtain different dose. The TL signals, which we have been obtained by using the converters, are increases to 71%. So we can resolve the neutron and gamma in mixed field.
The aim of this paper is determine the concentration of the organic oxygen in some organic compounds (Aldehydes ) by the derivative neutron activation analysis technique, and the derivative of the oxygen by the nitrogen equivalent toit and the irradiation of anew sample in flounce (1.73*106 n.cm-2.s-1) by the neutron generator .Then the calculation of the radioactivity which is done by using NaI(Tl) . After that we determine the concentration of nitrogen by calibration curve that includes nitrogen compounds which have apparent chemical and physical characteristics .For comparison the result is done by using keldal method.
The fractional free volume (Fh) in polystyrene (PS) as a function of neutron -irradiation dose has been measured, using positron annihilation lifetime (PAL) method. The results show that Fh values decreased with increasing n-irradiation dose up to a total dose of 501.03× 10-2 Gy.
A percentage reduction of 2.14 in Fh values is noticed after the initial n-dose corresponding to a percentage reduction in the free volume equal to 42.14/Gy.
The total n-dose induces a percentage reduction of 7.26, corresponding to a percentage reduction of 1.45/Gy. These results indicate that cross -linking is the predominant process induced by n-irradiation.
The results suggest that n-irradiation induces structure changes in PS, causing cross-linking
Applying load to a structural member may result in a bottle-shaped compression field especially when the width of the loading is less than the width of bearing concrete members. At the Building and Construction Department – the University of Technology-Iraq, series tests on fibre reinforced concrete specimens were carried out, subjected to compression forces at the top and bottom of the specimens to produce compression field. The effects of steel fibre content, concrete compressive strength, transverse tension reinforcement, the height of test specimen, and the ratio of the width of loading plate to specimen width were studied by testing a total of tenth normal strength concrete blocks with steel fibre and one normal s
... Show MoreMultiple drilling problems are being faced continuously while drilling wells in the southern Iraqi oil fields. Many of which are handled poorly and inefficiently which yields longer non-productive time due to the lack of knowledge about the source of these problems. This study aims to investigate the Basra oil fields formations from Faris to Mishrif, diagnose the potential problems, and present the optimum treatment for each problem.
Gathering of field data and previous studies on the subject, in addition to the field experience of drilling supervisors were all the information bases of this study. Southern Iraqi oil fields were studied and analyzed care
In this paper we generalize Jacobsons results by proving that any integer in is a square-free integer), belong to . All units of are generated by the fundamental unit having the forms
our generalization build on using the conditions
This leads us to classify the real quadratic fields into the sets Jacobsons results shows that and Sliwa confirm that and are the only real quadratic fields in .
The calculated neutron yields from (α, n) reactions are very important in analyzing radiation shielding of spent fuel storage, transport and safe handling. The cross sections of 63Cu (α, n) 66Ga and 65Cu (α, n) 68Ga reactions are calculated for different α-energies using different sets of programs using Matlab language. The values deduced energy is from threshold to Eα= 30 MeV and to Eα= 40 MeV for 63Cu (α, n) 66Ga and 65Cu (α, n) 68Ga respectively. The weight average cross section was then used to calculate the neutron yields y0 (n/106α) for each reaction .The empirical formula was then suggested to calculate total neutron yield to each isotope.