لبنى عبد الرسول مهدي الاسدي

In the current search, we have reported the theoretical analysis by utilizing DFT (TDDFT)- B3LYP at 6-31G (d, p) level on the geometries, optoelectronic and absorption characteristics of novel series of the donor-π-acceptor dyes. The π-conjugated bridge is based on the thiophene, benzene, pyridine, and pyrazine; the thieno [2,3-b] indole has been used as an electron donor (D) and theeacida2-cyanoacrylic has been used as an electron acceptor (A) group. The theoretical information of the electronic structures, such as energy levels (HOMO and LUMO) and energy gap of the molecules, is based on studying the dyes in organic solar cells. Consequently, the energy levels, energy gap, photovoltaic properties, quantum chemical and absorption parameters of all the dyes have been computed and reported. The calculations show that the dyes under study can theoretically be good photosensitizers in DSSCs. Moreover, the results indicate that the LUMO levels of all dyes design lie over the conduction band (Ecb) of the semiconductors TiO2 (or PC70BM) likewise the HOMO levels lie under the decrease potential vitality of the I−/I3 − (electrolytes) in comparison to the ability of electron transfer from the molecular dye excited state to TiO2 (or PC70BM) and chargeerenewal after photo-oxidation process, separately.

This chapter deals with gamma background radiation that is exposed to two major natural sources: normal sources that are earthly gamma rays and astronomical rays. Earthbound gamma rays from radionuclide elements such as thorium, potassium, and uranium. Also, in building and enhancing materials such as medical plants, building purposes, some vegetables and fruits commonly used in markets and soil. The measurements of gamma background radiation differ according to the purpose. So, there are many instruments used such as HPGe detector, NaI (TI) detector, CR-39, a dosimeter, and SSNDT detector. This research will explain in detail the studies and the mechanism for each detector and how it works and the application (practical) studies for each one. The purpose of calculating gamma background radiation is to be in the safe side for human being according to the international union specified with a standard limitation of world average value or with a specific value ranged (standard values) according to the case study in medical, food, or building materials.

A background radiation dose at indoor and outdoor of medicine and engineering faculties laboratories were calculated in Kufa University at Al-Najaf governorate, Iraq. Measurements were obtained using a portable dosimeter survey “Inspector Alert model RAP RS1, S.E. international, Inc,USA”. Amount of minimum and maximum mean dose radiation were ranged from (19.622 to 69.904nGy/h ) and from (8.277 to 16.249nGy/h ) respectively. The Annual Effective Dose indoor and outdoor were calculated between (4.466 and 0.259mSv/y) successively. So, it’s found lower than 1 µSv/y ,Which is recommended by UNSCEAR (2000) ; therefore, these values are found to be safe.

A background radiation dose at indoor and outdoor of medicine and engineering faculties laboratories were calculated in Kufa University at Al-Najaf governorate, Iraq. Measurements were obtained using a portable dosimeter survey “Inspector Alert model RAP RS1, S.E. international, Inc, USA”. Amount of minimum and maximum mean dose radiation were ranged from (19.622 to 69.904nGy/h) and from (8.277 to 16.249nGy/h) respectively. The Annual Effective Dose indoor and outdoor were calculated between (4.466 and 0.2S9mSv/y) successively. So, it's found lower than 1 μSv/y, Which is recommended by UNSCEAR (2000); therefore, these values are found to be safe.

In this research,

Indoor and Outdoor absorbed dose rates were measured in select region of AL-Qizweenia Najaf in Iraq. Measurements were perform using a Portable dosimeter Survey (Inspector Alert Model RAP RS1,S.E.international,Inc, USA). The results show that the values of absorbed dose indoor and outdoor were ranged from 696 to 1592.1 nGy/hr and from 565.5 to 1070.1 nGy/hr respectively. The average absorbed dose indoor and outdoor rates were 950.91 nGy/hr and 810.84 nGy/hr of every buildings and laboratories. According to occupancy factor of 0.8 and 0.2, the corresponding average annual effective dose indoor and outdoor rates were calculated to be, 4.66 mSv/yr and 0.99 mSv/yr, successively. The mean annual effective dose outdoor rate is found to be higher than 1mSv/yr which is the recommended dose limit for the public.

In this study, the calculation of Frenkel pairs generated as a result of irradiation of (Tungsten Carbide – Cobalt) alloys with nitrogen ions to different ratios of cobalt concentration, The value of radiation doses were(3.7 X〖10〗^19- 1.5X〖10〗^21 N/〖cm〗^2). The hypothetical irradiation was made using nitrogen ions with different energies between (120-180 keV) and a special program was written in "fortran power station 90" to obtain the theoretical results. According to this study,it was found that increasing in nitrogen ions energy causes increase of T(Max) and decreasing in Frenkel pairs generated by nitrogen ions from the range (120-180)keV, and the best increase was at energy (120keV)in tungsten and limited increase in other two types of atoms ( carbon and cobalt) ,because it's affected by another factors such as changing in temperatures and the ratios of cobalt concentration . These Frenkel pairs are generating dislocations and deformations in crystal lattice which in turn lead to an increase the hardness of these alloys.

Biscuit is important type of food that is widely consumed by baby in Iraq and other countries. This work measurers the natural radioactivity duo to long-lived gamma emitters in Children biscuit by gamma spectroscopy, and estimates radiation hazard indices which are the radium equivalent activity, the representative of gamma level index, the internal hazard index and annual effective dose in children. Ten samples were collected from the Iraqi market for different original countries. The average of specific activities for 226Ra, 232Th and 40K were (9.390, 3.1213 and 214.969) Bq/kg respectively, but the average of the radium equivalent activity and the internal hazard index were 33.101 Bq/kg and 0.107 respectively. The total average of annual effective dose from consumption of adult, child and infant is estimated to be 0.655, 1.009 and 0.875 mSv respectively

In this research, the Uranium (U-238), Thorium (Th-232) and Potassium (K-40) with the specific activity (10) in some types of legumes that are available in the Iraqi market samples had been measured and the internal hazard index, radium equivalent and the annual effective dose of K-40 in all samples were determined. The gamma spectrometry method with a NaI(Tl) detector was used for radiometric measurements. It was found that the specific activity in legumes varied from 1.450±0.096 to 12.307±0.387 Bq/kg (average of 7.475 Bq/kg) for U-238, from 0.371±0.058 to 9.289±0.465 Bq/kg (average of 3.79941 Bq/kg) for Th-232, and from 64.096±1.037 to 603.397±8.757 Bq/kg ( average 385.2477 Bq/kg) for K-40. The results were compared with international recommended values and were found to be within the international level.