السيرة الذاتية 

الاستاذ الدكتورعباس جواد عبد أحمد السعدي

((ProfessorPh.D. Abbas Jawad Al– Saadi

محل وتاريخ الولادة :   العراق – ديالى- الخالص  1964م

الحالة الزوجية:  متزوج                                              

اللغات : العربية – الانكليزي

التخصص العام:دكتوراه علوم في الفيزياء 

التخصص الدقيق : فـيـزياء نووية إشعاعية

محل العمل : جامعة كربلاء – كلية طب الأسنان

اللقب العلمي: أستاذ

البريد الالكتروني :abbasj6@yahoo.com

الوظائف والدرجات العلمية :

1. مدرس مساعد – جامعة الأنبا ر من 3/11/1991م   ولغاية 11/11/1994م.
2. مدرس – جامعة الأنبا ر من 12/11/1994م   ولغاية 10 /8/1999م.
3. مدرس- جامعة صنعاء – كلية العلوم  من 23/3/ 2000م   ولغاية  15/7/2009 م .
4. استاذ مساعد – جامعة كربلاء – كلية العلوم من 27/7/2009 – 1/9 /2011 م.
5. استاذ مساعد – جامعة كربلاء –  كلية طب الأسنان من 1/9/ 2011 م  – 2/10 /2014 م.
6. رئيس فرع العلوم الطبية الاساسية –  كلية طب الأسنان 2011-2012
7. – مسؤول الوحدة البحثية في  كلية طب الأسنان
8. استاذ – جامعة كربلاء –  كلية طب الأسنان من 3/10/ 2014 م.
9. بكالوريوس علوم في الفيزياء (.)  جامعة بغداد 1987م. الأول على قسم الفيزياء.
10.  ماجستير فيزياء نووية إشعاعية ((  M.Sc. جامعة بغداد 1990م. اطروحةالماجستير: توزيع الفيض النيوتروني في مواد وتراكيب مختلفة من الدروع الواقية.
11. دكتوراه  فيزياءنوويةإشعاعية ( .( Ph.D جامعة بغداد 1997م . اطروحة الدكتوراه: دراسة تاثير أشعة  كاما على الخواص الفيزيائية لبعض العوازل الكهربائية البولمرية.

 الشهادات العلمية:

        

الخبرة التدريسية :

أولا : لطلبة الدراسات العليا ( الماجستير) :

  الفيزياء الإشعاعية  –   جامعة صنعاء – كلية العلوم

ثانيا : لطلبة الدراسات الأولية : ( مرتبة في الجدول  أدناه) 

البحوث المنشورة(Published researches)  

1. Abbas J.  Al-Saadi  “Measurement of Removal Cross Sections 14MeV Neutrons for Al, Fe and H₂O ”  Al-Mustansiriya J.Sci.Vol.6, No.1(1996) p. 32-34.

Abstract

     The attenuation of 14.5MeV neutrons in different materials (Al, Fe and H₂O) was determined, using NE-213 detector for detection the primary neutrons. The attenuation of primary neutron flux in selected materials was defined by simple exponential relation based on removal cross section. The experimental values of removal cross section were agreement with theoretical values. The deviation between present results and earlier data obtained by other authors can be explained by geometry difference of the measurements.

2. Abbas J.  Al-Saadi “Gamma Radiation Effect on Electrical and Mechanical Properties of Polystyrene” Journal of Deiala for Science and Education, Vol.1, No.3 (1998) p.21-32.

Abstract

       Polystyrene sheets were irradiated with gamma radiation emitted from radioisotope ⁶⁰Co. The sheets were submitted to different radiation doses (5-50) kGy. The gel fraction was found to be increase with increasing radiation dose. Electrical properties of irradiated polystyrene  included Conductivity, Dielectric constant and loss factor in frequency range(1-1000) kHz. The increasing of   Conductivity and loss factor were explained on the basis of degradation and crosslinking phenomena. Stress –strain curves of Polystyrene sheets were determined which indicated that Young modulus increase with increasing radiation dose. In addition structure studies viscosity and IR spectroscopy.

3. Abbas J.  Al-Saadi “Optical Analysis of un dyed Poly (Methyl Methacrylate) for high Dosimetry” IBN Al-Hathem  Journal of Pure and Applied Science Vol. 9, No. 2 ( 1998) p.60-70.

Abstract

      The response of un dyed Poly (Methyl Methacrylate PMMA) gamma radiation to gamma radiation were investigated, with the aim of providing a dosimeter based on spectrophotometry measurements. It is found that 1mm thick of PMMA can be used a dosimeter in arrange of absorbed dose range (5-50) kGy. The optical absorbance at wavelength 285nm was linear function with radiation dose. The effect of post irradiation storage time on the spectrum was also investigated.

4. Abbas J.  Al-Saadi and R. Al Kubasi “Effect of Gamma ray on poly Vinyl chloride” IBN Al-Hathem  Journal of  Pure and Applied Science Vol. (12),  No.(3) ( 1999) p.53-61.

Abstract

     High gamma doses produce various structural changes poly vinyl chloride (PVC).     X-ray diffraction and molecular weight for PVC samples previously exposed to gamma radiation emitted from ⁶⁰Co were investigated.  Degradation predominantly occur At radiation doses below 50 kGy, while at radiation doses above 50kGy crosslinking and degradation phenomena take place in sequence. The reaction products such as carbonyl groups seem to be produced by the gamma ray interaction with PVC polymer.

5. Abbas J.  Al-Saadi “Empirical Formula to Fit Gamma Ray Buildup Factor Values in Water”  Faculty of Science Bulletin Vol.18 (2005) p.169-173.

Abstract

       Experimental measurements of gamma ray buildup factor have been made for point gamma ray isotopes ¹³⁷Cs and ⁶⁰Co in water up to depths of 4mean free path (mfp). The experimental values of buildup factor were computer fitted as a function of penetration depth using three degree polynomial formula. Those buildup factor data were found to agree well with theoretical calculations with an error less than 5%. These results indicate that the our empirical formula is able to provide gamma ray buildup factor with an accuracy enough to be used in shielding calculations.

6. Abbas J.  Al-Saadi “Iron Polyethylene Combination for Shielding of 14MeV Neutrons” Journal of  Kufa – Physics VOL.2 NO.1 (2010) p.1-5.

Abstract

      The best way to a chive good shielding of 14 MeV neutrons was investigated. The idea is to thermalize as many neutrons as with a given shielding thickness. Since hydrogenous material is not efficient for thermalization of 14 MeV neutrons, the neutrons are first slowed down with iron to energy rang where hydrogen is more efficient for thermalization. Layers of iron and polyethylene of various thicknesses that add up to 20 cm were investigated and it was found that a composition of 10 cm of iron before 10 cm of polyethylene gives the highest number of thermal neutrons. The fast neutron flux leading out of the shielding is decreasing continuously with increasing iron thickness.

7. Abbas J.  Al-Saadi “Determination of neutron relaxation length in borated polyethylene and concrete” Proceeding of the 6^th Sci. of K.U. (2010) P. 84-91. 

Abstract

     The relaxation length for 14 MeV neutrons emitted from   fusion reaction in borated polyethylene ( ρ = 0.96 g. cm^-3, 10% wt. boron ) and concrete                             ( ρ = 2.35 g. cm^-3) were determined. Measurements were made by using liquid organic scintillation detector type NE 213. The response rate of detector to 14 MeV neutrons transmission from borated polyethylene (BPE) and concrete with different thickness were measured. For each material, an average value for the neutrons transmission representing exponential decrease during passage through the considered range of layer thicknesses. The experimental results are found agree well with theoretical calculations.

8. Abbas J.  Al-Saadi  “A study of  14 MeV  neutrons  buildup factor in paraffin wax, graphite and lead ” Journal of Karbala University, Vol. 9, No.3 (2011) p.223-229.

Abstract

     The 14 MeV neutrons buildup factor  in paraffin wax, graphite and lead have been experimentally determined using the BF3 counter up to a thickness of 2.5 mean free path    ( mfp ).The dependence of the secondary neutrons spectrum transmitted from all selected materials on the thickness at the fixed incident neutron energy has also been studied using a liquid organic scintillation detector type NE 213. Results indicate that, the value of buildup factor remains close to unity up to penetration depths of 0.4 mfp and then increases when sample thickness increased. The neutron spectra obtained in this research depends  on the material type and thickness. In general, the neutron spectra decrease with increasing sample thickness. Comparison of the experimental results obtained with the previously calculated neutron buildup factor shows a good agreement. 

9. Abbas J. Al-Saadi “Calculation of buildup factor for Gamma ray exposure in two   layered shields made of water and lead” Journal of Kufa physics Vol.4, No.1 (2012) p.1-10.

Abstract

     The exposure gamma ray buildup factor is most useful in calculations for biological protective shields. The exposure gamma ray buildup factors were calculated in two layered shields consist of water – lead and lead – water up to optical thickness 20 mean free path( mfp ) at gamma ray energies 1, 2 and 6 MeV by using kalos’s formula. The program has been designed to work at any atomic number of the attenuating medium, photon energy, slab thickness and the order of materials. The results obtained in this search leading to the exposure gamma ray buildup factor at energies ( 1 and 2 MeV ) in lead-water is higher than the reverse case, while at energy 6 MeV the effect is opposite. The calculated data were parameterized by an empirical formula as a function of optical thickness of two materials. The results obtained are in reasonable agreement with a previous work.

10. Abbas J.  Al-Saadiand Abbas, K. Saadon  “Using gamma ray transmission for determination of porosity in doped alumina samples” IBN Al-Hathem Journal of Pure and Applied Science, Vol.25, No.1 (2012)  p.174-179 .

Abstract

         In this study, gamma ray transmission method have been used to determine the total porosity in four samples: pure Alumina ( Al₂O₃ ), Al₂O₃ + (0.2wt%)MgO ,                   Al₂O₃ + (0.6wt% )Y₂O₃ and Al₂O₃+(8wt% ) ZrO₂ . The experimental setup for the gamma ray transmission consist of  ¹³⁷Cs gamma source ( 662 keV), NaI (Tl) scintillation detector measured the attenuation of strongly collimated gamma beam through alumina samples. The porosity obtained by the gamma ray transmission method was compared with the measurements by conventional (Archimedes) method. It was observed that the porosity measurement by gamma ray transmission method has the advantage of being accurate, nondestructive and fast analysis.                                                                                   

11.Abbas J.  Al-Saadi “Calculation of partial and total cross sections for gamma photon interactions” International Journal of Development, Vol.1, No. 1 (2012 ) p.29-41.

Abstract

      This object of the present work was to determine the partial cross sections of photoelectric effect, coherent ( Rayleigh ) , incoherent ( Compton )  scattering and pair production (in nuclear field and in electron field ) as well as total cross sections for deferent atomic number ( 20, 40, 60, 80, and 100 ) at gamma energy range ( 10^-3 -10⁵ MeV ), using XCOM code. Furthermore, the total cross section of Al, Fe and Pb at gamma energies (0.6616, 1.1732 and 1.3325 MeV) emitted from radioactive point sources ¹³⁷Cs and  ⁶⁰Co were measured, using NaI(Tl) scintillation detector. The results obtained have showed that the calculated and measured partial and total cross section values are sensitive to the incident photon energy and atomic number of target material. The results were in good agreement with calculated values.

12. Abbas J.  Al-Saadi “Measurement of mass attenuation coefficient for wood at gamma energy range 186 – 1765 KeV”  Journal of the college of basic education, Vol.18, No. 75 (2012) p.167- 172.

Abstract

     Mass attenuation coefficient values for Swedish board wood ( ρ = 0.5065.g.cm-3  )  at gamma energies 186.2,  242,  295.2, 351.9,  609.3, 768.3, 1120.3, 1238.1 and 1764.5 keV were measured by using HPGe detector. The radiation source used in the experiment    was  . These coefficients were also calculated by XCOM code. The experimental result obtained gives good agreement with calculated values. The mass attenuation coefficient for Swedish board wood obtained in this research was  decreased with increasing photon energy.

13. Abdal Sattar K. Hashimand Abbas J.  Al-Saadi “Radon Measurements in Different Types of Carbonated Drinks in Iraq“Journal of Karbala University, Vol. 10 , No.4 (2012) p. 41-46.

Abstract:

       In this study, the concentrations of radon (²²²Rn) radioactive isotope in different types of carbonated drink samples, as well as, in sterilized drinking water were determined. Measurements were made, using long-term technique for alpha particles emission with solid state nuclear track detector type CR-39. Twelve types of different carbonated drinks were brought from local markets in Iraq. The results showed that Radon concentrations in carbonated drinks samples were ranging (1.771 – 5.642) Bq/L; while the average value was (3.835Bq/L). The highest concentration was found in peach drink samples, whereas the lowest concentration was in the orange flavored drink. Also that radon concentration in sterilized drinking water was measured 1.642 Bq/L. However, these values were lower than allowed maximum contaminant level (MCL) for (222Rn) in drinking water as reported by USA Environmental Protection Agency (EPA) which is about 11.1 Bq/L.

14. Abbas J.  Al-Saadi and Abdal Sattar K. Hashim  “Measurement of Radon and Uranium Concentrations in the Dates and their Seeds of Different Regions in Karbala Governorate”Journal of Babylon University/Pure and Applied Sciences, Vol.(21),No.(6),: (2013) p.2134-2147.

Abstract

      The radon (²²²Rn) and uranium (²³⁸U) concentrations in dates (kistawi and zahdi brands) and their seeds were experimentally determined by using solid state nuclear track detector CR-39. Samples were collected from twelve sites in Karbala governorate of mid region in Iraq. Heat drying method was used to concentrate the radioactive nuclides in measured samples. Sealed-cup technique employed to measure ²²²Rn. The results obtained have shown that the average radon gas concentration in kistawi dates samples was found to be 187.242 Bq/m³ while the average radon gas concentration was found 197.477 Bq/m³ in zahdi dates samples. The average uranium concentration in kistawi dates samples was         1.439 ppm, while in zahdi dates samples it was 1.540 ppm. We also found that the average value of radon concentrations in kistawi seeds samples was 199.242 Bq/m3 and in zahdi seeds samples was 205.348 Bq/m³. The average uranium concentration in kistawi seeds samples was about 1.509ppm, while in zahdi seeds samples it was about 1.578ppm.

 The present results have shown that the radon gas concentration in all dates and their seeds samples is below the permissible limit from (International Commission of Radiation Protection) (ICRP) agency.

15. Abbas J.  Al-Saadi “Determination of Radon Concentration and the Annual Effective Dose in Karbala University Campus, Karbala, Iraq” Karbala J. Med. Vol.6, No.1, June,

(2013) p.1591-1599.

Abstract

         Determination of radon gas concentrations in multistory buildings and outdoor in the Karbala University campus (Karbala-Iraq) were carried out by using Solid-state nuclear track detector (CR-39).The detectors were distributed over 20places (14 indoor and others outdoor). The area of the study includes College of Medicine, College of Dentistry, College of Pharmacy, College of Sciences, student’s residence and the Central Library. The dosimetric measurements were made over a period of 3 months. (from 15 September to 14 December 2012). After exposure, the detectors were etched in a (NaOH) solution of normality (6.25 N) at temperature of 70 ^oC for 3 hours. The tracks were counted by the microscope track-counting system. The indoor radon gas concentrations were found to vary from 41.881 ± 2.463Bq/m³ to 95.642 ± 5.730 Bq/m³ with an average value and standard deviation of 70.358 Bq/m3and14.367Bq/m³ respectively. The outdoor air radon concentrations are ranged from 25.134 ± 1.783Bq/m³ to 28.594 ± 2.854Bq/m³ with an average value of 26.974 Bq/m³and standard deviation of 1.155 Bq/m³. In the survey of radon concentration in multistory buildings was observed that the upper floor have lower radon concentration than the ground floor. It has found that, in general, the radon level in lower floors is higher than that in upper ones in all buildings. The annual effective dose to the population from the inhalation of radon was also estimated and this varied from 1.056 ± 0.062mSv/ y to 2.412 ± 0.144mSv/ y, with an average of1.774 mSv/y and standard deviation is 0.362mSv/ y. The ratio between indoor and outdoor radon concentration (mean value) in this study was about 3.The radon concentrations were found to be lower than the higher level recommended by ICRP ( 200 Bq/m3) and thus are within safe limits.

16.  Abbas J. Al-Saadi “Energy Absorption Buildup Factor in A Few Human Tissues and Tissues-Equivalent Plastic”  Karbala J. Med. Vol.7, No.1, June( 2014) p.1806-1817.

Abstract

background: Energy absorption buildup factor inhuman tissues are very important for the researchers working to help in estimating safe dose levels for radiotherapy patients and useful in radiation therapy, diagnostics, and dosimeters.

Aim: The main emphasis has been focused on the dependence of energy absorption buildup factor on the incident photon energy, penetration depth and effective atomic number (Z_eff )in the human tissues and tissues equivalent plastic.

Materials and Methods: Energy absorption buildup factor in a few human tissues such as skin, brain, striated muscle and compact bone as well as in tissue-equivalent plasticA-150 and bone- equivalent plasticB-100have been computed using the five parameter geometric progression(G.P) fitting formula in the energy range of 0.015-15 MeV up to penetration depth 40 mfp. The half value layer (HVL) for selected tissues were also estimated.

Results & Discussion: The variation of energy absorption buildup factor for selected tissues has been studied as a function of incident photon energy, penetration depth and effective atomic number(Z_eff).The energy absorption buildup factor increases with increasing photon energy and reaches a maximum value at gamma ray energy range(0.1-0.2MeV), then start decreasing further with the increasing photon energy. There is continuous increase in energy absorption buildup factor with increase in penetration depth.

Comparison of calculated energy absorption buildup factor with standard database from ANSI/ANS6.4.3-1991 (American National Standard, 1991) shows good agreements.

Conclusion: Variation in value of energy absorption buildup factor was due to dominance of different interaction processes in different energy regions and chemical compositions of the human tissues. In general, the energy absorption buildup factor is lower for compact bone and bone equivalent plastic B-100 at photon energy range (0.015- 1 MeV) .

17.  Abbas J. Al-Saadi  ” Variation of gamma ray attenuation parameters for Poly vinyl alcohol reinforced by lead acetate” Journal of Kerbala University , Vol. 12 No.3 Scientific (2014) p.35-44.

Abstract

       Design types of shielding polymers to protect patients and personnel from the effect of

scattered radiation during radiotherapy. Some shielding factors were calculated such as mass attenuation coefficient (μm), half value layer (HVL), effected atomic number (Zeff ) and heaviness for polyvinyl alcohol (PVA) as matrix material mixed with various levels of lead acetate (10 – 50 wt. % ) as reinforced materials at photon interactions in the wide gamma ray energy range of 0.001-100 MeV using XCOM program and measured at 0.662 MeV by usage a 137Cs radioactive source. The experimentally obtained values were generally in good agreement with the theoretical ones. The results revealed that the shielding properties of poly vinyl alcohol increased with the addition of lead acetate. Gamma ray shielding properties of our polymer samples have been compared with standard ordinary concrete. It was found that 20wt.% of lead acetate (CH₃COO)₂ Pb  is the minimum percent mixed with PVA improves the gamma ray shielding properties best than standard ordinary concrete (NIST).

18.  Abbas J. Al-Saadi “Study of exposure and energy absorption buildup factor for some building materials available in Iraq” Journal of  Kufa – Physics Vol.6/ No.2 (2014)  p.59-68.

Abstract

       Exposure buildup factor (EBF) and energy absorption buildup factor (EABF) for some building materials (cement, clay brick, thermiston, gypsum and ordinary concrete) available in Iraq at the photon energy range 0.015-15.0 MeV up to penetration depth 40 mfp has been calculated using five parameter geometric progression (G.P) fitting formula. The variation of EBF and EABF with incident photon energy, penetration depth and equivalent atomic number (Z_eq) for the selected building materials has been studied. Variation in value of EABF was due to dominance of different interaction processes in different energy regions and the chemical composition of studied materials. Also, the half value layer of chosen building materials has been computed as a function of incident photon energy. It was observed that concrete has well gamma ray shielding materials than other selected building materials.

19.  Abbas J. Al-Saadi  and Abbas K. Saadon “Gamma Ray Attenuation Coefficients for Lead oxide and Iron oxide Reinforced in Silicate Glasses as Radiation Shielding Windows” Ibn Al-Haitham Jour. for Pure & Appl. Sci. Vol. 27(3) (2014) p.201-2014.

Abstract

     In this work, the mass attenuation coefficient, effective atomic number and half value

layer parameters were calculated for silicate (SiO₂) mixed with various levels of lead oxide and iron oxide as reinforced materials. SiO₂ was used with different concentrations of PbO and Fe₂O₃ (25, 50 and 75 weight %). The glass system was prepared by the melt-quenching method. The attenuation parameters were calculated at photon energies varying from 1keV to 100MeV using the XCOM program (version 3.1). In addition, the mass attenuation coefficient and half value layer parameters for selected glass samples were experimentally determined at photon energies 0.662 and 1.28 MeV emitted from radioactive sources ¹³⁷Cs and  ²²Na respectively in a collimated narrow beam geometry set-up using 2″x2″ NaI (Tl) scintillation detector. These values are found to be in agreement with the values computed theoretically. Moreover, these results were also compared with those for the commercial window glass. The effective atomic number         ( Z_eff ) and half value layer (HVL) results indicate that pbO+SiO₂was better gamma ray attenuation than Fe₂O₃+SiO₂ and commercial window glass. This indicates that PbO+SiO₂ glasses can be used as gamma ray shielding in replace of both of them in this energy range.

20. Abbas J. Al- Saadi, Abdal  sattar  K. Hashim and Hayder J. Musa “ Determination of radium and radon exhalation rates in soil samples collected from Karbala governorate” International journal of physics, Vol. 3 No. 5, 2015 p.208-2012.

Abstract    

       In the present work, radium concentration and radon exhalation rates in soil samples collected from Karbala Governorate area (Iraq) have been measured through “Sealed cup technique” containing CN-85 solid state nuclear detector. This area is honorable position in the entire world, millions of peoples and religious sciences students visit it, in addition the soil of this area was used in brick manufacturing for building construction. Radium concentration varies from (1.1001- 2.6003) Bq/kg with an average of 1.7921Bq/kg. The radon exhalation rate in terms of area varies from (0.9463 – 2.2369)  Bqm-2h-1 with an average of 1.4785Bqm-2h-1, while radon exhalation rate in terms of mass varies from (29.715– 70.237) ×10-3  Bqkg-1h-1 with an average of 48.409×10-3 BqKg-1h-1. Positive correlation has been observed between radium concentration and radon exhalation rate in soil. The values of radium concentration in all the soil samples were less than the limit     370 Bqkg-1 as recommended by Organization for Economic Cooperation and Development (OECD) 1979, thus results revealed that the area is safe as far the health hazard effects are concerned.