Coupled-channels optical model code OPTMAN is used as an alternative to experimental approach to evaluate the total reaction cross section for eight selected isotopes of heavy rotational nuclei of the transuranium elements over an energy range of 10 to 20 MeV. The selected isotopes are the ₉₃Np²³⁷, ₉₄Pu²³⁸, ₉₄Pu²⁴⁰, ₉₄Pu²⁴¹, ₉₄Pu²⁴², ₉₅Am²⁴³, ₉₆Cm²⁴⁴ and ₉₅Am²⁴⁵. Their choice is as a result of their importance in the modern day nuclear reactor and the energy range 10 – 20 MeV is the energy range of neutron produced in neutron generators and the maximum energy possessed by neutrons which are born in fission reaction. Results show that the percentage deviation of total cross section from ENDF values obtained for this work is less than 1 % at 14 MeV and above for ₉₃Np²³⁷ and at 16 MeV and above for ₉₄Pu²³⁸, ₉₄Pu²⁴⁰, ₉₄Pu²⁴¹ and ₉₅Am²⁴³ while at 18 MeV and above for ₉₄Pu²⁴², ₉₆Cm²⁴⁴ and ₉₅Am²⁴⁵. This work observed that the nucleus of transuranium elements is symmetric and the activities of rotation and vibrations (β – quadrupole, octupole vibrations and γ – quadrupole vibrations) cannot be ignored. Deductions in terms of parity in the transuranium elements revealed that the effects of the collective characteristics are exhibited by the neutrons and countered by the protons. This work compared well with the 6 % of Basunia in 2009 and 5 % of Paradela in 2011 using indirect measurement based on the surrogate ratio method and ECIS code respectively and is found to agree with about 1.3 % increase in accuracy.

O02: DOUBLE DIFFERENTIAL PROTON EMISSION CROSS SECTIONS FOR STRUCTURAL FUSION MATERIALS ²⁴ Mg

G. Demirelli^1*, I.H. Sarpun¹, E. Tel², A. Aydin³

¹Afyon Kocatepe University, Physics Dept., Afyonkarahisar Turkey

²Osmaniye Korkut AtaUniversity, Department of Physics, Osmaniye, Turkey.

³Kirikkale University, Physics Dept., Kirikkale, Turkey

^*isarpun@gmail.com

Abstract

In this study, double differential proton emission cross sections of ²⁴Mg target nuclei have been theoretically calculated by the TALYS 1.8 code at 14 MeV neutron incident energy. Theoretical calculated cross sections were compared with available experimental data in EXFOR library. Furthermore, in theoretical calculations direct, compound and pre-equilibrium reaction contribution have been investigated. Theoretical and experimental values are in good agreement for all emission angles.

O03: NEUTRON PRODUCTION CROSS–SECTION CALCULATIONS FOR SOME GAMMA AND PROTON INDUCED REACTIONS ON ⁸⁹Y

A. Kaplan¹, M. Şekerci¹, B. Demir²

¹Süleyman Demirel University, Department of Physics, Isparta, Turkey

²Istanbul University, Department of Physics, Istanbul, Turkey

Abstract

Neutron moderation for nuclear applications has an undeniable importance. To be able to moderate neutrons, one of the important step is to choose the convenient material. The material’s response for different type of nuclear reactions, define its possibility and availability for using as a neutron moderator material. The cross–section data of a reaction, which could be expressed as the probability of a reactions occurrence, could provide many benefits in the cases of the experimental difficulties or unsuitable conditions. For such cases, theoretical calculations obtained via verified methods are highly acceptable. In this study, ⁸⁹Y, which is a neutron moderator material used in nuclear reactors, has been investigated and neutron production cross–section calculations for some gamma and proton induced reactions on ⁸⁹Y have been done in the energy interval of 6–772 MeV with two most known and accepted calculation codes, TALYS 1.8 and EMPIRE 3.2. The Two Component Exciton and Exciton models have been used within the codes, respectively. Obtained results by using both code’s mentioned models and exist experimental data taken from EXFOR database have been compared with each other.

O04: DENSITY DEPENDENT NEW CROSS SECTION CALCULATIONS OF ¹⁰BORON TARGET NUCLEI

E. Tel¹, I.H. Sarpun², M. Sahan¹, A. Aydin³, A. Bulbul¹

¹Osmaniye Korkut AtaUniversity, Department of Physics, Osmaniye, Turkey

²Afyon Kocatepe University, Physics Department, Afyonkarahisar, Turkey

³Kirikkale University, Physics Department, Kirikkale, Turkey

eyuptel@osmaniye.edu.tr

Abstract

There are many applications for Boron element such as medical, industry, energy etc. Boron neutron capture therapy (BNCT) is the most important medical aplications for cancer theraphy. In this study, by using new method, neutron induced nuclear reactions calculation of Boron target nuclei have been investigated in the incident neutron energy at 14-15 MeV. Also the cross sections with Skyrme force parameters were calculated for ¹⁰B target nuclei for neutron induced nuclear reactions. We calculated reaction cross section using Tel et al. formula with Skyrme and Skyrme like force. We compared with obtained data from EXFOR around 14-15 MeV.

O05: K-SHELL INTERNAL CONVERSION COEFFICIENT OF g-RAY TRANSITION IN Ba^*137

J. Jose^1,2, S. B. Gudennavar¹^*, L. Francis Maria Anand^1,3 and S. G. Bubbly¹

¹Department of Physics and Electronics, Christ University, Bengaluru-560029, India

²Department of Physics, Christ Junior College, Bengaluru-560029, India

³Department of Physics, Government First Grade College, K. R. Puram, Bengaluru, India

^*Corresponding author: shivappa.b.gudennavar@christuniversity.in

Abstract

An unstable nucleus disintegrates into a more stable configuration through any of radioactive decay processes such as alpha decay, beta decay and cluster decay, which leaves the product nucleus in an excited state. This excited nucleus decays further to the ground state either through a radiative process (called g-decay) or through non-radiative process (called Internal conversion process (IC)). In IC process, the electromagnetic multipole fields of the nucleus interact with an electron from one of the orbits of daughter atom causing that to be emitted. The probability of such an event occurring is negligibly small. The vacancy created in a shell due to IC process leads to the emission of various characteristic X-rays. The IC process is quantified by defining internal conversion coefficient (ICC) as the ratio of number of internal conversion electrons to number of γ-rays emitted by the nucleus. Study of internal conversion process throws a light on the knowledge of electric or magnetic multipole character of the nucleus (electric multipole or magnetic multipole transition) and the energy dependence of multipole transitions. Precise values of ICCs are necessary in establishing the accurate decay schemes of nuclei and also provide a versatile tool for investigating various aspects of the nuclear structure. From the literature, we understand that most of previous measurements have made use of a γ-ray detector for detecting γ-rays and an electron detector for detecting conversion electrons separately to determine ICCs. Hence this procedure is too involved. Given this, in the present work, we have made an alternative effort where we measure the intensities of γ-ray and K shell X-ray photons from Ba¹³⁷simultaneously using HPGe detector and use the recent best values of K shell fluorescence yield for Ba¹³⁷to determine ICCs. From the measured intensities of K X-rays of barium and the g-rays, we determined the K-shell internal coefficient for barium. The result was compared with available experimental values from other methods and theoretical value. The close agreement found paves an alternative way of measurement of ICCs.

O06: STOPPING POWER OF PROTONS FOR ENERGIES AND MATERIALS OF THERAPEUTIC IMPORTANCE USING MONTE CARLO SIMULATIONS

A. Bozkurt¹ and I. H. Sarpun²

¹Antalya, TurkiyeAkdeniz University, Faculty of Engineering, Department of Biomedical Engineering,

²Afyon Kocatepe University, Faculty of Arts and Sciences, Department of Physics, Afyonkarahisar, Turkey

abozkurt@akdeniz.edu.tr

Abstract

This study presents the results of Monte Carlo simulations to obtain stopping power of protons in energy ranges and materials of therapeutic importance. The source was modeled as a point source emitting mono-energetic pencil beam of protons. A cylinder containing the material of interest was placed in vacuum to represent the phantom, a cylinder of 30 cm radius and 100 cm height. A disk-shaped thin detector (r=2 cm) was created in this phantom to compute average values of absorbed dose and flux. Its thickness varied from simulation to simulation depending on the energy of the incoming source protons. Average flux and absorbed dose were computed in the detector cell to evaluate the value of the stopping power for the material of interest at that specific energy. The results obtained in this study are compared with the data from the NIST compilation.

O07: SHELL CLOSURE NUCLEI N = 82 STUDYING AND INTERPRETATION: CERIUM ISOTOPES ^136-138CE

S. Kaim¹ and A. Abboudi

¹Université des Frères Mentouri – Constantine1. Route Ein Elbey. Constantine 25017.

Abstract

The motivation of this work is the theoretical studying of some nuclei of the shell closure (N =82), cerium isotopes ^136-139Ce, in the frame of macroscopic-microscopic CNS model (Cranking Nilsson Strutinsky) which calculates the following properties: single particle energy, total energy, liquid drop energy, moments of inertia, angular momentum, electric quadrupole moments, deformation parameters, nuclei shape, potential energy surfaces (PES),…

We have studied the high spin rotational bands of these isotopes using the proposed configuration and we have found a good agreement comparing with the observed results of the recent works.

O08: PRELIMINARY SURVEY OF ACTIVITY CONCENTRATION OF NORM IN SOIL SAMPLES FROM RICHARDS BAY, SOUTH AFRICA.

Felix B. Masok¹ , Paulus L. Masiteng¹, Risimati D. Mavunda², Peane P. Maleka³, Hartmut Winkler⁴

¹University of Johannesburg, Applied Physics and Engineering Mathematics Department, P.O Box 17011, Doornfontein 2028, South Africa

²South African Nuclear Energy Corporation (Necsa), PO Box 582, 0001 South Africa

³Department of Nuclear Physics, iThemba LABS, National Research Foundation, P.O.Box 722, 7129 Somerset West, South Africa

⁴Department of Physics University of Johannesburg, Auckland Park 2006, South Africa

* Correspondence;fmasok@yahoo.com(+27-762-864-786)

Abstract

Uranium-238 (²³⁸U) and thorium-232 (²³²Th) are the parent primordial nuclides who along with their progenies are sources of radiation exposure to which humans are exposed directly or indirectly. In this study, sixty soil samples were analyzed for ²³⁸U and ²³²Th concentration using neutron activation analysis (NAA). The samples were irradiated by thermal neutrons in NECSA’s nuclear research reactor. The mean gross alpha and gross beta activities were found to be 597 Bq.kg^-1and 518 Bq.kg^-1 respectively. The activity concentrations of primordial radionuclides (²³⁸U and ²³²Th) in the analyzed soil samples were found to be below the safety limits set out by International Council on Radiation Protection (ICRP).

O09: Radiolysis of pharmaceuticals in wastewater using irradiation technology

W. Jahouach-Rabai¹^,2, Z. Azzouz-Berriche², R. Lahsni³,B. Habibi³, A. Ghrabi¹

¹Center of Water Research and Technologies, Echopark Borj Cedria, Tunisia

²National Center of Nuclear Sciences and Technologies, Technopark Sidi Thabet.

³Society of Pharmaceutical industries of Tunisia (SIPHAT), Z.I. Ben Arous, Tunisia.

Corresponding author:Wafa.Jahouach@gmail.com

Abstract

Widely used pharmaceutical compounds have been detected in environmental systems, essentially in water. In this purpose, the degradation efficiency of these pollutants was evaluated using an advanced oxidation process (AOP) as an alternative to conventional water treatment technologies. This process permitted the generation of radical reactions to directly degrade organic contaminants in wastewater. In fact, gamma irradiation of aqueous solutions produces several reactive radicals, essentially hydroxyl radical (^.OH), to destroy recalcitrant pollutants.

Pharmaceuticals considered in this study are paracetamol, aspirin, ibuprofen, diclofenac, fumaric acid and dichloroaniline at different concentrations 0.1-1 mmol/L, which were treated by irradiation doses from 3 to 15 kGy with 6.1 kGy/h rate by ionizing system in pilot scale (₆₀Co irradiator). Main parameters influencing degradation efficiency were considered in the aim to optimize total mineralization of pollutants. Variation curves of main parameters (UV absorbance, COD, pH,…) versus absorbed doses describing the experimental data were released. Preliminary degradation mechanisms are suggested based on analytical study using different techniques, namely EPR, FTIR, GC-MS and HPLC. Results revealed pharmaceuticals destruction until total mineralization, which improve the efficiency of this process in water remediation. Finally, pilot plant and industrial scale irradiation facilities improved the applicability of radiation technology on large scale.

Keywords:AOP, Gamma irradiation, hydroxyl radical, EPR, HPLC, FTIR, GC-MS.

O10: INDUSTRIAL WASTEWATER TREATMENT USING HIGH ENERGY ELECTRON BEAM IRRADIATION: REMOVAL OF CHROMIUM (VI) HEAVY METAL

F. Djouider¹ and M. S. Aljohani¹

¹Nuclear Engineering Department, Faculty of Engineering, King Abdulaziz University Po Box 80204, Jeddah, 21589, Saudi Arabia

Abstract

Chromium(VI) heavy metal is a major water contaminant, due to its carcinogenicity, while Chromium (III) is non-toxic and is an important for human metabolism. Large quantities of Cr(VI)-contaminated wastewater are discharged into aquatic environments. The objective of this study is to evaluate the removal of Cr(VI) by O₂ˉ^•free radicals.

The degradation of Cr(VI) was investigated by electron beam irradiation using a 2.5 MeV van de Graaff accelerator. Pulse durations of 2 μs were used. The dose obtained was 500 Gy per pulse. The bleaching of Cr(VI) was observed spectrophotometrically at 370 nm.

The degradation of Cr(VI) increased linearly with the absorbed dose. More than 99% of Cr(VI) was removed after a dose of 5 kGy at near neutral pH. A partial recovery of Cr(VI) is observed over a period of 5 ms.To explain the mechanism of this removal, a kinetic model was proposed.

This laboratory study shows that electron beam irradiation might be effective and economical in the remediation of large volumes of industrial wastewater contaminated with chromium. It is an alternative means to conventional chemical methods of treating effluents

O11: MICROEXTRACTION OF URANIUM AND NUCLEAR FORENSIC ANALYSIS BY CHEMOMETRIC BASED LASER ABLATION MOLECULAR ISOTOPIC SPECTROSCOPY (LAMIS)

J. N. Malaba¹, F.O. Oduor², H. K. Angeyo³

^1,2Department of Chemistry, University of Nairobi, P.O Box 30197 Nairobi, Kenya

^3,Department of Physics, University of Nairobi, P.O Box 30197 Nairobi, Kenya

Abstract

Nuclear forensics (NF) is increasingly becoming important in nuclear security and the fight against illegal trafficking of nuclear and radiological materials (NRM). Current analytical challenges call for rapid direct methods that achieve high accuracy and discrimination of NRM of limited size. Laser induced breakdown spectroscopy (LIBS) is extremely attractive in this regard, but can neither easily perform accurate trace nor isotopic analysis. Chemometrics assisted laser ablation molecular isotopic spectroscopy (LAMIS) overcomes this as well as that of isotopic analysis limitation as the plasma exhibits large isotopic splitting (enhanced using chemometrics) due to contributions of the rotational and vibrational states of ablated molecules. We have developed a method for micro-extracting uranium from model NF scenarios by combining solid phase and dispersive liquid-liquid micro-extraction and subsequent LAMIS. A recovery of 70% was achieved. The lines identified for LAMIS were U I 682.6 nm and U II 424.4 nm. Principal component analysis (PCA) was used to discern patterns due to isotopic composition. Subsequently multivariate calibration strategies for quantitative isotope ratio estimates were developed utilizing artificial neural network (ANN) and support vector machines (SVM). We will describe our method and its application in trace uranium NF analysis and source attribution based on the isotopic characteristics.

O12: Uncertainty and Sensitivity analysis of LBLOCA transient in CALLISTO loop using SUSA code

A. Hadjam¹, D. Saad², H. Boucherit³, H. A. Kaliatka⁴,T. Kaliatka⁵, M. Valinčius⁶

^1,2Nuclear Research Center of Birine, B.P. 180 Ain Oussera,17200, Djelfa, Algeria

³Nuclear Research Center of Draria, BP 43, Sebala, Draria, Algiers, Algeria

^4,5,6Lithuanian Energy Institute, Laboratory of Nuclear Installation Safety -Kaunas, Lithuania

Corresponding author:hadjam.ahmed@yahoo.fr

Abstract

In this paper, we studied the uncertainty and sensitivity analysis of RELAP5 results for CALLISTO loop Large Break LOCA accident using the statistical uncertainty analysis methodology namely SUSA code. This analysis was performed using a one-sided upper limit tolerance limit for the fuel cladding temperature and one-side lower limit for the critical heat flux ratio (with 0.95 probability and 0.95 confidence) respectively. According to Wilk’s formula in order to reach such probability and confidence limits at least 59 code runs should be performed. Each code run includes different sets of initial and boundary conditions defined in the input for the code. The uncertain parameters are defined as random values generated from the interval of values with a defined probability distribution function. Thus, prior to performing uncertainty analysis the list of parameters that could influence the results is created, the intervals of values and probability distribution function are defined for each parameter, law of normal distribution was used to evaluate the potential margins. It is assumed that each parameter is independent and the sets of initial and boundary conditions for each code run are created. Uncertainty parameters for this case of study of CALLISTO loop stability margin calculation is presented with eleven (11) uncertain parameters were chosen. The main safety parameters for the uncertainty and sensitivity analysis of the CALLISTO loop following the LBLOCA accident are the maximum fuel cladding temperature and the minimum critical heat flux have been studied and discussed.

Keywords: CALLISTO, LBLOCA, SUSA, RELAP5, Uncertainty, Sensitivity

O13: Interaction of a Gaussian laser beam with an acousto-optical cell

A.Benstiti¹, K.Ferria¹, A.Bencheikh^1,
2

¹Applied optics laboratory, Institute of optics and precision mechanics, Algeria

²Al Bachir Al Ibrahimi University, BordjBouArréridj, Algeria

Abstract

Most scientific, medical and industrial applications of lasers cannot be satisfied by a beam having a Gaussian intensity distribution in a transverse plane. In this case, it is then necessary to transform the intensity profile of the Gaussian laser beam. A solution is the introduction along its path of an acousto-optical cell (AO) whose phase profile ϕ(x,y) will allow, after diffraction, the desired shape in the focal plane of a lens. The spatial characteristics of the diffracted beam produced by this AO cell were studied theoretically. The complex amplitude distribution of a diffracted beam is described using Collins integral and ABCD matrix formalism. The obtained results show that the output intensity profile differs from that of the incident Gaussian beam and takes the form of a flat top beam or a hollow beam, for specific values of the acoustic pressure represented by the parameter y inside the AO cell and the truncation parameter K_a, defined as the ratio of the acoustic wavelength to the width of the laser beam.

O14: UV-VIS SPECTROSCOPY OF Eu³⁺ AND Gd³⁺ IONS DOPED YPO₄

S. Hachani¹, L. Guerbous², A. Zemiri³, K. Djelloul³

¹Laboratoire de Physique Photonique et Nanomatériaux Multifonctionnels, FSESNV, Université de Biskra, BP 145 RP, 07000 Biskra, Algérie

²Département Laser, Centre de Recherche Nucléaire d'Alger, CRNA, 2 Bd., Frantz Fanon, BP 399 Alger, Algérie

³Département SM, FSESNV, Université de Biskra, BP 145 RP, 07000 Biskra, Algérie

Abstract

This work is part of the quest for new phosphors with quantum yield greater than one under VUV excitation. It is concerned with UV-Vis spectroscopy properties study of Eu³⁺ and Gd³⁺ ions doped YPO₄. We indexed 4f energy levels of those ions and Eu³⁺ CTB. Gd³⁺ ion emission is weak and situated in UV range at 310 nm correponding to ⁶P_7/2 → ⁸S_7/2 transition. That of the Eu³⁺ ions has a strong intensity and situated in the visible range (red-orange) corresponding to ⁵D₀®⁷F_J transitions. ⁶P_7/2 (Gd³⁺) and ⁵D₀ (Eu³⁺) excited-states lifetimes are 4.21 ms and 3.47 ms respectively. Our study indicates that YPO₄ : Eu³⁺, Gd³⁺ may have potential applications in lighting and display.

O15: NEMA NU-2 2012 PERFORMANCE EVALUATION OF THE FIRST PET-CT SYSTEM INSTALLED IN ALGERIA

A. Toutaoui, M. Belmessaoud, S. Bencheikh, R. Louelh

Département de Radiothérapie et d’Imagerie Moléculaire, Hôpital Chahids Mahmoudi,Tizi Ouzou, Algeria

Abstract

The combination of a positron emission tomograph (PET) with an x-ray computed tomograph (CT), in a single hybrid PET-CT system plays an important role in diagnosis, staging and treatment response evaluation of a large range of tumors due to the possibility of obtaining, in a single study session an accurate spatial registration of functional (PET) and morphological (CT) images. The clinical applications of PET-CT have been expanding, mainly in oncologic diagnosis and management but the development of new radiotracers is opening a new scenario also for PET-CT in cardiology and neurology.

The evaluation of PET performance requires reproducible and reliable methods to allow the comparison of different systems using accepted measurement standards. The National Electrical Manufactures Association (NEMA) has published a series of procedures to evaluate the physical performance of PET systems.

In this work, the performance characteristics of the PET component of the Discovery IQ 3 rings PET-CT scanner are investigated according to the NEMA protocol NU2-2012. This is the first PET-CT installed in Algeria at Hôpital Chahids Mahmoudi. The NEMA NU2-2012 standard was used for spatial resolution, sensitivity, scatter fraction, image quality and count loss measurements when images were reconstructed with a new algorithm called Q-Clear.

O16: Investigation of the initial and volume recombination losses in gamma versatile ionization chamber VGIC developed for gamma ray dosimetry

M.Fares¹, S.Mameri¹, M. Y. Debili², A.Bouranane K.Negara

1Laboratory of Nuclear Detectors / Department Detection and Measurement/DEDIN/DDM, Commissariat for Atomic Energy, Nuclear center Research of Birine, PO Box 180, Ain Oussera, 17200. W. Djelfa

2LM2S, Physics Department, Faculty of Science, Badji-MokhtarUniversity, BP 12 Annaba 23200, Algeria.

E-mail: fares2005_fr@yahoo.fr

Abstract

Gamma ionization chambers are used for gamma flow control in nuclear reactors and reprocessing plants in and monitoring atmosphere around these facilities, this in order to protect staff. In our Laboratory Detection and Measures (LDM/DEDIN/CRNB, we designed, developed and characterized a versatile gamma ionization chamber (VGIC) to study experimentally its characteristics according to the geometry of the electrodes, the volume and pressure of the filler gas. The tests were conducted under the IEC (International Electro-technical Commission).

In this paper, we present the results obtained in the various nuclear tests for characterization and calibration that we have madeon the VGIC prototype developed in our Laboratory. To do this, three irradiators were operated at the Laboratory Calibration (SSD/CRNA).The first Irradiator intensive gamma (⁶⁰Co: 1.25 MeV), the second medium intensity gamma (¹³⁷Cs: 0.662MeV) and the 3^rd low intensity (⁶⁰Co). Saturation curves and linearity were identified and the operating range and the sensitivity of the chamber have been deducted.

The (I,V) characteristics of the chamber filled, with argon gas at 3bar pressure, were studied. The plateau region is reached above 200 V and the detector operating voltage is found to be 600V. It is observed that in the plateau region the slope is constant with an increase in the exposure rate. The (1/I, 1/V) and (I, l/V²) characteristic curves reveal the presence of the initial and volume recombination losses. The volume recombination losses are found to be smaller than the initial recombination losses.

Finally, in order to strengthen our results, we performed in the same conditions, a comparative characterization with another ionization gamma chamber type reference LND 504 (USA).

Keywords: IonizationChamber, Flux Gamma,dose rate, Sensitivity

O17: THE DOSE RATE MEASUREMENTS OF C-ARM FLUOROSCOPIC X-RAY SYSTEMS WITH AND WITHOUT APRON

N. Tuncel^1,2

¹Akdeniz University, School of Medicine, Radiation Oncology Department, Antalya/ TURKEY

²Akdeniz University, Science Faculty, Physics Department, Antalya/ TURKEY

ninatuncel@gmail.com

Abstract

C-arm fluoroscopic X-ray systems are used for a variety of diagnostic imaging and minimally invasive surgical procedures. In the operating room, they help in visualizing kidney drainage, abdominal and thoracic aortic aneurysm repair, gastroenterology, orthopedics, neurology and other procedures. There have been few studies evaluating the dose of radiation received by health professionals who use these systems. The present study was embarked upon to analyze the amount of radiation received by them using standard precautionary measures and also to bring awareness about the use of standard lead apron (5mm thick) and adequate distance for safety in everyday practice. The measurements were performed at maximum kV and mA for determination of dose rate with and without lead apron for different distances from X-ray unit at the level of patient position. The Geiger–Müller counter with end-window detector was used for measurements. Reduction of risks due to ionizing radiation can be achieved by various practices, which involve the design and usage of equipment, use of targeting devices and certain measures that can be taken by the personnel involved. So, it provides good safe usage of this type of X-ray unit.

O18: RADIATION TRANSMISSION THROUGH LAMINATED BARRIER FOR HIGH-ENERGY LINEAR ACCELERATORS USED IN RADIOTHERAPY

R. Bechchar and J. ghassoun¹

¹⁾ EPRA, Department of physics, Faculty of Sciences Semlalia

PO Box: 2390, 40000 Marrakech, Morocco

E-mail address: ghassoun@uca.ma

Fax: 212 5 24 43 74 10

Abstract

The purpose of radiation protection is to reduce doses to acceptable level. Shielding is one of the most effective means of reducing radiation exposure. For high-energy linear accelerators, the materials typically used for shielding of radiotherapy room are ordinary concrete. However, in most cases, adding metals to the primary barriers is the best alternative to shield rooms properly.

In this work, the equivalent dose distributions and the transmission factors curves through laminated barrier with concrete, iron , lead and steel , for high energy linear accelerator (> 10 MV), were studied. The required shielding thicknesses to reduce the photon dose to within acceptable limits were determined using point kernel method combined with an appropriate buildup factor. The dose buildup factors of different shielding materials were determined using the geometrical progression (GP) method. The difference of the dose equivalent attenuation between the concrete shield alone and the lead + concrete + iron + steel shielding arrangement were determined.

The obtained results are in good agreement with published data reported in the literature. Also, it was observed that the use of a laminated barrier leads to a significant reduction of transmitted doses than using concrete shield alone.

Keywords: Shielding; Dose buildup factor; Transmission; Barrier; Linac; Dose; GP method.

O19: Photodynamic Therapy and cancers, current state and perspectives in Algeria

A. Oulhissane¹, A. Baba Ahmed²

1Faculty of Sciences, Abou Bakr Belkaid University, Tlemcen, Algeria

2 Faculty of Medicine, Djilali Liabes University, Sidi Bel-Abbès, Algeria

Abstract

The Photodynamic Therapy (PDT) is a technique intended to handle certain type of cancers. The application is dated 1975.

It is based on the action combined of an actionable photosensitizing molecule (PS), a light Laser of appropriate wavelength and of theoxygen naturally present in the biological environment. Laser radiation will activate PS preferentially fixed to cancer cells and causes the death of tumoral cells by releasing toxic radical species that will then alter vital targets of tumoral cells.

The PDT had its major developments in the 1980s, when several clinical teams, mainly in the USA, in Canada and in Japan showed its efficiency in the treatment of certain tumors, generally inoperable.

Given that this technique is not during the day in Algeria, in particular in the coverage of the cancer, the certain doctor’s biophysicists, oncologists, dermatologists and others, want to put a lot into this domain. However, the PDT can be a standard therapeutic modality only if there is awareness of all the healthcare professionals and to benefit so on one hand from the financing granted within the framework of the cancer plan by public authorities.

This work was the subject of the dissertation of Master of Professional Medical Physics.

Keys words:Cancer, Phototherapy, Photosensitizer, Oxygen, Laser, Free Radicals, Cell Death.

O20 : Large pixelated CZT versus conventional NaI(Tl) gamma camera

N. Boutaghane¹^{, 2}, B. Bouzid¹, H. Zaidi^3,4,5,6.

¹Laboratoire SNIRM, Faculté de Physique, USTHB, BP 32 El-Alia BabEzzouar, Algeria

²Département de physique, Université les frères Mentouri-Constantine1, Ain El bey, 25000 Constantine, Algeria

³Division of Nuclear Medicine and Molecular Imaging, Geneva University Hospital, CH-1211 Geneva, Switzerland

⁴Geneva Neuroscience Center, Geneva University, CH-1205 Geneva, Switzerland

⁵Department of Nuclear Medicine and Molecular Imaging, University of Groningen, University Medical Center Groningen, 9700 RB Groningen, Netherlands

⁶Department of Nuclear Medicine, University of Southern Denmark, DK-500, Odense, Denmark

Abstract

Semiconductor CZT detectors are deemed to outperform NaI(Tl) scintillation crystals owing to direct photon conversion, high atomic number and large band gap energy. The aim of this work is to investigate parameters reflecting imaging system performance, including the combination detector/collimator characteristics. To this end, a comparative study between NaI(Tl) scintillationcamera equipped with a standard LEHR collimator and a large pixelated CZT system with a hole matched collimator was performed using GATE Monte Carlo modeling. The preliminary comparison results of the NaI(Tl) vs large CZT systems showed a spatial resolution of 7.4 mm and 11.5 mm, sensitivity of 158.2 cpm/µCi and 1087.2 cpm/µCi, central reconstructed spatial resolution in air of 8.6 mm and 12.7 mm (using OSEM reconstruction algorithm with resolution recovery), and of 10.2 mm and 13.3 mm in water, respectively. The superior performance of the large CZT system has been demonstrated using equal hole collimator length. The preliminary results of this study show that an optimal combination of detector and collimator characteristics could be proposed for a new CZT clinical imaging system.

Keywords: GATE, CZT system, SPECT, parallel hole collimator.

O21: LIGHT CHARGED PARTICLE EMISSION OF B₄C COMPOSITES

I.H. Sarpun¹, A. Bozkurt², A. Aydin³, S. Pat⁴

¹Afyon Kocatepe University, Physics Dept., Afyonkarahisar, Turkey.

²Akdeniz University, Engineering Faculty, Antalya, Turkey.

³Kırıkkale University, Physics Dept., Kırıkkale, Turkey.

⁴Eskisehir Osmangazi University, Physics Dept., Eskişehir, Turkey

isarpun@gmail.com

Abstract

Composites play an important role in the nuclear energy researches due to their excellent thermal and mechanical properties. In fission and fusion nuclear reactor structural material researches, composites, especially ceramic composites are suitable as structural materials. The mechanical strength of composites increases with temperature, in contrast to the strength of metal and ceramics.

In this study, B₄C composites, produced in Eskisehir Osmangazi University by RF plasma sputtering technique in dimension of 1cm x 1cm, used as target material to obtain light charged particle, proton, deuteron and alpha, emission spectra by MCNPX.

*This work has been supported by Afyon Kocatepe University, Office of Scientific Research Projects 16.FENED.05

022: K-SHELL JUMP FACTOR AND JUMP RATIO OF 3d ELEMENTS

L. Francis Maria Anand^1,2, S. B. Gudennavar^1*, S.G. Bubbly¹, B. R. Kerur³ and L. D. Horakeri⁴

¹Department of Physics and Electronics, Christ University, Bengaluru, India

²Department of Physics, Government First Grade College, K. R. Puram, Bengaluru, India

³Department of Physics, Gulbarga University, Kalburagi, India

⁵Department of Physics, S. K. Arts College and H. S. Kotambri Science Institute, Vidyanagar, Hubli, India

* Corresponding author: shivappa.b.gudennavar@christuniversity.in

Abstract

Gamma photons when interact with matter through photoelectric effect with incident energy just above the K-shell electron binding energy, a steep increase in the photoelectric absorption energy near the K edge is seen as a saw tooth structure. The saw tooth structure demarcates the lower energy branch for L and higher shells from the upper energy branch for the K-shell. Theoretically, the ratio of photoelectric absorption cross section of the upper branch to that at the lower energy branch for a given element is the K-shell jump ratio and jump factor. We, in the present work, have experimentally determined the K- shell jump factor and jump ratio by measuring the K X-ray production cross-section and the K X-ray intensity ratio for a few pure 3d elements, Co, Ni, Cu and Zn employing a simple 2p-geometrical configuration method. Adopting this method,the target elements were excited using 32.86 keV K X-ray photons from a weak ¹³⁷Cs radioactive source. The emitted K X-rays from the targets were detected using a low energy HPGe X-ray detector spectrometer with a energy resolution of 200 eV at 5.9 keV. Acquired spectra were analysed origin software and determined the K X-ray intensity ratio, jump factor and jump ratio for these elements. The results from the present work were compared with reported values theoretical and experimental values establishing a close agreement. The uncertainty in the measured values of jumpfactor and jump ratio for all of the target elements is less than 2%.

O23: Measurement of radon exhalation rate and natural radioactivity in the northern areas of Punjab, Pakistan

S. A. Mujahid, M. Akram and P.O. Nilore,

Islamabad, Pakistan

Email: shafiq_mujahid@hotmail.com

Abstract

The track-etch detectors were used to measure the radon concentration and exhalation rates from the soil samples collected from the areas of northern Punjab, Pakistan. The radon concentrations and the radon exhalation rate were found in the ranges 30 – 270Bq.m^-3 and 40 - 295 mBq.m^-2.h^-1respectively. The measurements of natural radioactivity in the soil samples of these areas has also been carried out using HPGe detector. The radiological hazards due the naturally occurring radionuclides were also assessed. The measured activities of ²²⁶Ra, ²³²Th and ⁴⁰K were found in the range of 19–40, 26–60 and 510–700 Bqkg⁻¹, respectively. The calculated absorbed dose rate in air and the annual effective dose were in the range of 45–85 nGyh⁻¹ and 0.22–0.41 mSv, respectively. The values of internal and external hazard indices were in the range 0.3-0.6 and 0.2-0.5, respectively.

O24 : HEALTH HAZARDS RELATED TO URANIUM CONCENTRATION IN DRINKING WATER COLLECTED FROM NATURAL SPRINGS OF THE JHELUM VALLEY, AZAD KASHMIR – PAKISTAN

M. Akram¹, A. Iqbal², N. U. Khattak³, S. A. Mujahid, S. Hussain, M. U. Rajput, N. Zafar

¹ Physics Division, PINSTECH, Nilore, Islamabad 45650, Pakistan

² Physics Department, University of Azad Jammu and Kashmir, Muzaffarabad, Pakistan

³National Centre of Excellence in Geology, University of Peshawar, Peshawer, Pakistan

Corresponding author E-mail akram1662@gmail.com

Abstract

Besides being radioactive, uranium is also chemically toxic and may be hazardous if ingested in higher concentration. Quantitative determination of uranium in drinking water is therefore, highly desirable. In this context, drinking water samples were collected from natural springs of the Jhelum valley, Azad Kashmir. All the collected samples along with the standard were first dried over the LexanÒ detectors and were then irradiated with thermal neutrons in the Pakistan Research Reactor-1 (PARR-1). After irradiation, the detectors were etched in 6M NaOH solution at 50 ^◦C. From the measured track densities in samples and standard, uranium concentration in water samples was determined. The observed uranium concentration in the studied samples ranged from 5.55 mgL^-1 to 164.05 mgL^-1 with an average value of 20.88 mgL^-1. The comparison of observed uranium concentration with Maximum Acceptable Concentration levels set by different monitoring agencies of the world as well as with the results from other locations reported in the literature indicates that there are some samples having uranium concentration above safe limits. However, in most of the cases, uranium concentration is within safe limits as far as uranium related health hazards are concerned and that the general public is safe for using water from these springs

O25: NEW METHOD FOR DETERMINATION OF REEs BY NEUTRON ACTIVATION ANALYSIS FOR SOIL REDISTRIBUTION STUDY

A. Azbouche¹, M. Belamri¹, M. Belgaid²,

¹Nuclear Research Center of Algiers, 02, Bd. Frantz Fanon, B.P. 399, 16000, Alger-Gare, Algiers, Algeria

²USTHB, Faculté de Physique, Laboratoire SNIRM, B.P. 32, El-Alia, 16111, Bab Ezzouar, Algiers, Algeria

Abstract

Rare Earths Elements (REEs) are good tracers for the study of the process of erosion and soil redistribution in watershed. Neutron Activation Analysis is one of the best methods for determination of REEs (La, Nd, Eu, Tb, Yb, Hf) with low detection limit. In this work, a new model was developed by using the Instrumental Neutron Activation Analysis, based on capture reaction (n,γ) corrected by the contribution (n,fission) reaction, for determination of REEs in the soil. A combination of an experimental approach and Monte Carlo calculation by using MCNP5 has been used to establish the parameter of irradiation and measurement. The HPGe detector's parameters were optimized by comparing the values of efficiency measured with those obtained by Monte Carlo (MCNP5) simulations. A good agreement between Monte Carlo and experiment results was found. The irradiation parameters were measured experimentally for the φ_thand φ_epi correction by using the reaction:

For apply this model in the soil redistribution, the samples were irradiated at nuclear reactor under a neutron flux of 2.36 10¹³cm^-2.s^-1 for 04 hours and measured by gamma spectrometry, using a high resolution HPGe semi-conductor detector with (1.8 keV for⁶⁰Co 1332.5 keV line). The spectra were analyzed using the Genie 2000 software dedicated to the processing of gamma spectra.

The determination of the concentrations of REEs with high precision, these results allowed us to identify areas of erosion and accumulation in the studied watershed.

Keywords: Monte Carlo MCNP5, Irradiation and Measurement parameters,INAA,REEs, Soil redistribution.

O26: TRACE ELEMENTS INVESTIGATION AND QUALITY ASSESSMENT IN SOIL SAMPLES BY INAA

Z. Bouhila, A. Nedjar, T. Azli, D. Boukhadra, A. Hadri

Nuclear Research Center of Draria (CRND/COMENA), Sebala, Draria PO Box 43, Algiers, Algeria

Abstract

In this analytical work, some components of soil samples collected in different locations were determined by instrumental neutronactivation analysis (INAA). The concentrations of more than 30 minor and trace elements (Sr, Zr, Cd, As, Ca, Br, Mo, W, Ga, La, K, Sm, Nd, Sb, Sc, Zn, Cr, Fe, Hf, Ta, Tb…) in the samples were measured. The samples were irradiated under a neutron flux of 2 × 10¹³ n cm⁻² s⁻¹, during 6 h for long and medium half-life radioisotope determination in NUR research reactor at Draria City in Algiers, which operates at a power of 1 MW. The induced activities were counted by gamma ray spectrometry using an efficiency calibrated High Purity Germanium (HPGe) detector. Trace element concentrations were examined in top soils to evaluate the contribution of the anthropogenic sources in the enrichment of these elements in the soil surface layer. The results were compared with literature values from other countries and the obtained data in most of the case did not exceed the normal levels. For the evaluation of the performance of the assay and the meaning of the results, the z-score, was used to make a quality assessment of our study using certified reference materials (CRM). The laboratory performance is evaluated as satisfactory if Z score ≤ 2, questionable for 2 < Z score < 3 and unsatisfactory for Z score ≥ 3. The analytical results of the comparison ofour measured data with recommended values for two reference materialsfor most of the elements, in both the materials,were within ±1. The results are in good agreement with the recommendedvalue of CRM standards.

Keywords: Instrumental neutron activation analysis (INAA), Trace element, certified reference materials (CRM), z-score.

O27: DEGRADATION MECHANISM OF A GLASS/UNSATURATED POLYESTER COMPOSITE EXPOSED TO GAMMA RADIATION

N. Belloul¹, K. Boumerdassi¹, B. Kouini¹, A. Ahmed Benyahia², D. Haouanoh³, A. Serier¹

¹ Laboratory of Coating, Materials and Environment (LRME); University M’Hamed Bougara,Boumerdes, 35000, Algeria.

² Advanced Mechanic Laboratory (LMA), University of Sciences and Technology HouariBoumediene (USTHB),Bab Ezzouar 16024, Algeria.

³ Research unit: materials - processes and environment (UR-MPE),University M’Hamed Bougara, Boumerdes, 35000, Algeria.

Abstract

The aim of this work is to understand the degradation mechanism of a glass/unsaturated polyester (UP) composite exposed to γ radiation and to establish a relation between the chemical and mechanical behaviour of this material.

Mere visual observations show a marked change in the color of the (UP) resin and the composite, relative to the irradiation dose. This change of color disappears with time and the material resumes its initial color (post-irradiation phenomenon). FT-IR spectral analysis of the irradiated resin reveals a change in its molecular structure which depends on the irradiation dose. This would involve the formation of a new oxygenated groups (OH and COOH) appears in the resin structure due to an oxidation reaction under aerobe irradiation. The peaks corresponding to the C=C of the styrene and the polyester are, also, affected by the cumulative dose, what indicate the chains rupture or cross linking. As for the results of the mechanical characterization, they revealed a cyclic character in the evolution of the engineer constants. This periodicity would indeed reflect a kind of alternation in the emergence of the two phenomena cross linking and chains rupture within the material depending on the increase in the irradiation dose.

O28: EVALUATION AND OPTIMISATION OF TREATMENT PLANS USING RADIOBIOLOGICAL MODELS

O. D. Osahon¹ and G. E. Okungbowa²

1Department of Physics, Faculty of Physical Sciences, University of Benin, Benin City, Edo State, Nigeria.

2Department of Radiography and Radiation Science, School of Basic Medical Sciences, College of Medical Sciences, University of Benin, Benin City, Edo State, Nigeria.

Abstract

This study evaluated and optimized treatment plans of post mastectomy patients using radiobiological models. It is a retrospective study of twenty three (23) post mastectomy patients whose Computerised Tomography (CT) scans have gone through Computerised Treatment Planning in University of Benin Teaching Hospital (UBTH) Radiotherapy Unit from 2012 – 2014. Patients that have undergone chemotherapy were excluded from the study.

The study revealed that the treatment plans had high local tumor control on the target breast (99%); while the NTCP models for the lungs gave higher complication probability than the heart. Also, there was difference between the linear, linear-exponent and linear-plateau dose risk models for SCCP; the linear dose risk model deviates more from the other two models which was due to the fact that majority of the patients were exposed to mean dose/Equivalent Uniform Dose (EUD) greater than 5 Gy to the lung and Planning Target Volume (PTV) to the heart. In optimizing the treatment plans the fractionation schemes gave NTCP values below the Quantitative Analysis of Normal Tissue Effect in the Clinic (QUANTEC) threshold of 5% for lung and 1% for heart and thus can be recommended for clinical trials.

O29: INVESTIGATION OF CABLE INSULATOR RESISTANCE TO g-RAY AND NEUTRON IRRADIATION

M. Izerrouken¹, Dj. Haddad¹, S. Berkani¹, T. Seguini¹, R. Zamoun¹, A. Ameur¹, H. Zirour²

¹Nuclear Research Center of Draria, Bp. 43 Sebbala, Draria, Algiers, Algeria

²University of science and technology Houari Boumediene , Faculty of physics, Bp 32 EL-Alia Bab-ezzouar,Algiers, Algeria

Abstract

The present investigation reports the resistance of the polyethylene cable insulator components to g- rays and neutrons irradiation. The studied cable is similar to that actually installed inside NUR research reactor tank, Algiers, Algeria. The g-ray irradiation were performed using ⁶⁰Co source of Nuclear Research Center of Algiers (CRNA) up to a dose of 5×10⁶ Gy with a dose rate of 1.2 kGy/h. Neutron irradiation were made at NUR research reactor of Nuclear Research Center of Draria (CRND) up to a thermal and fast (En >1.2 MeV) neutron fluence of 5×10⁹ n/cm² and de 2×10¹⁰ n/cm² respectively. The g-rays dose in this position is estimated to about 7.5 Gy. After irradiation the samples were characterized using Differential Scanning calorimetry (DSC) and Thermogravimetry (TGA-DTA). It is concluded from the experimental data that PE insulator presents a successful behaviour under neutron and high g-ray doses corresponding to the total exposure dose in nuclear reactor tank. But PVC jacket becomes far less durable under high g- ray doses which affect its reliability in nuclear reactor service environment.

O30: Study of the Proton Irradiation Effect on the Performances of the GaAs Solar Cell

S. Tahar¹ and A. Nouri²

¹Department of matter sciences, Exacts sciences Faculty, Amar TELIDJI University, UAT Laghouat, ALGERIA

²Department of matter sciences, Exacts sciences Faculty, Mohammed TAHRI University, Bechar BP 417, ALGERIA

Abstract

In this work, we study the effect of protons irradiation on a solar cell based on GaAs. The irradiation is modeled by the ion implantation of hydrogen ions. The implantation effect obtained is used to simulate the output characteristics of this solar cell. Interesting results are obtained showing the damage caused by the variation of the energy of the protons (increase in defects, decrease in efficiency and the current of the solar cell) to a depth of up to 6µm. However, there is not a significant change on the output parameters of the solar cell by the variation of the protons fluency.

O31: THERMAL HYDRAULIC TRANSIENT ANALYSISOF ACCIDENT SCENARIOFOR VVER440 USING APROS-6 COMPUTER CODE

Y. Bouaichaoui

Birine Nuclear Research Center/CRNB/COMENA/ALGERIABO 180 – Aïn Oussera - 17 001 – Djelfa- Algeria

Abstract

This paper presents the results of thermal-hydraulic analyses of three accident scenario calculated using the thermal-hydraulic system codes APROS in steady-state and during the transient : Small Break Loss of Coolant Accident (SBLOCA) Steam Line Break (SLB) and double-ended guillotine break accident in supporting of Symptom Based Emergency Operating Procedures.

This kind of analyses are designed to provide the response of monitored plant parameters to identify symptoms available to the operators, timing of the loss of critical safety functions and liming of operator actions to avoid the loss of critical safety functions or core damage.

The simulation model is a complete model of VVER-440 nuclear power plant developed at VTT Technical Research Centre of Finland in cooperation with Fortum for analyses of operational occurrences, abnormal events, and design bases scenarios. It includes all main process components and their control automation devices. The model provides a significant analytical capability of APROS-6 in the field of NPP safety.

O32: FREQUENCY OF DICENTRICS IN HUMAN BLOOD IRRADIATED IN VITRO

K. D. Aouragh, H. Amara-Hamai, M.K. Bach-Tobdji, A. Djefal-Kerrar and N. Ait Said

Centre de Recherche Nucléaire d’Alger, 2 Bd Frantz Fanon BP 399 Alger-Gare, Algérie

Abstract

Exposure to ionizing radiation can lead to alterations in the genetic heritage of the cell that can be transferred to daughter cells during cell division. Induced DNA damage will result in chromosomal aberrations despite the extremely effective repair mechanisms activated.

Chromosomal exchange type aberrations (especially dicentrics) analyzed from peripheral blood lymphocytes represent a biomarker of choice for radiation-induced lesions in a cell population and allow estimation of the dose received during accidental body irradiation.

Blood samples of healthy donors were irradiated in vitro with different doses (1-4 Gy) of 60-Cobalt gamma-rays. Human lymphocytes were cultured for 48h.The metaphase preparations are processed for Giemsa staining and analyzed by photonic microscope to scoring dicentrics.

Analysis of chromosomal aberrations in at least 200 cells for each dose, showed an increase of the frequency of dicentric chromosomes with the dose. The experimental dose-effect curve established is linear-quadratic.

Keywords: DNA, gamma rays, lymphocyte, chromosomal aberration, dicentric, biological dosimetry.

O33: PHYSICAL AND BIOLOGICAL EVALUATION OF 3D TREATMENT PLAN FOR PROSTATE CANCER

A. Boughalia¹, M. Fellah², S. Khoudri³, S. Haoui³, K. Boualga³

¹Medical Physics Department, Nuclear research of Algiers

²Université des Sciences et de la Technologie Houari Boumediene « USTHB », Alger

³ Radiotherapy-Oncology Department –Oncologie, Centre Anti-Cancer, Blida

Abstract

In order to evaluate the first 3D treatment plans calculated in the Radiotherapy-Oncology department of Centre Anti-cancer Blida, an in-house software was developed to compute Equivalent Uniform Dose (EUD).

28 patients were planed and treated for prostate cancer with 3D-CRT. A given dose of 70 Gy was prescribed and delivered in 38 fractions. Evaluation of these treatment plans was carried out using an in-house software based on computing EUD in case of tumor and organs at risk (OAR).

All results obtained for the treated patients show that EUD was maximum for targets and minimal for OAR compared to calculated dose given by the treatment planning system “TPS”. Indeed, EUD_mean(Target) = 82.45 (± 1.08) Gy, EUD_mean(Rectum wall) = 37.16(± 1.08) Gy, EUD_mean(Right Femoral Head) = 19.90 (±2.35) Gy, EUD_mean(Left Femoral Head) = 19.92 (±2.58) Gy and EUD_mean(Bladder wall) = 33.20 (± 1.6) Gy. The evaluation given by computing function EUD gives a maximum value of Tumor Control Probability TCP _mean(Target) = 99.93 (±0.016) %.

The evaluation of 3D plans is useful for physicist. For this purpose, the developed in-house software has been validated for prostate cancer and can be used for others type of cancer.

Keywords: Conformal Therapy “ 3D-RTC” , Equivalent Uniform Dose “EUD”, Tumor Control Probability “TCP”

O34: LONG-TERM CONSEQUENCE ON KIDNEY AND LIVER ORGANS OF IODINE-131 CONTAMINATED WISTAR RATS (WITH AND WITHOUT THYROID)

M. Mezaguer-Lekouaghet¹, A. Badreddine¹, S. Mameri², M. Souidi³, A. Baz⁴& Z. Lounis-Mokrani¹

¹Centre de Recherche Nucléaire d’Alger, Algérie

2 Centre Hospitalo Universitaire Mustapha Bacha Alger, Algérie
3 Institut de Radioprotection et de Sûreté Nucléaire Paris, France

4 Ecole Normale Supérieure de Kouba, Algérie

Abstract

Iodine-131 is considered one of the most frequently used radionuclides for diagnosis and radiotherapy of thyroid diseases. Its use in therapy has become a common practice especially with the increase in the frequency of thyroid cancer in the world. Although the thyroid is the target organ, iodine can transit and accumulate in other organs through the blood circulation in the body.

In this study we propose to evaluate the activity of iodine accumulated in kidney and liver organs at different periods (5, 24, 48 hours, 7 and 13 days after iodine orally administrated) for two Wistar rat models with and without thyroid. These activities have then been measured using gamma spectrometry technique and the respective organ's doses have been calculated. The consequences of iodine irradiation on tissue as well as organ function have been examinated using histological section and blood parameters measurement.

The results revealed for the kidney organ some disturbances, from inflammation to the presence of tissue fibrosis and glomerular necrosis, with disruption of certain parameters such as creatinine. For the liver organ, there is the appearance of inflammatory focus at different degrees around the door spaces accompanied by perturbations in the blood parameters.

O35: Development of calibration procedures of an Electronic Portal Imaging Devices a-Si 1000 used for IMRT and VMAT

A. Maachou¹, A. Toutaoui², N.Khelassi-Toutaoui¹, R. Louelh², Z.Sakhri-Brahimi¹ and A. C. Chami³

¹Département de physique Médicale, Centre de Recherche Nucléaire d’Alger

²Département de radiothérapie et imagerie moléculaire, Hopital Chahids Mahmoudi, Tizi Ouzou, Algeria

³Laboratoire SNIRM, Faculté de Physique, USTHB, BP 32 EL-Alia, Bab Ezzouar, Alger, Algerie

Abstract

In recent years Electronic Portal Imaging Devices (EPIDs) have become an indispensable tool for the patient veriﬁcation set-up in radiotherapy. Therefore, for their use in dosimetry, a calibration and an investigation into their physical characteristics is necessary. The aims of the present study is the development of calibration procedures and investigate the stability and the linearity of the signal of the portal imager a-Si 1000.

The measurements of the grey level pixels are carried out in the central axis of the beam. The EPID is calibrated by acquiring an image (DF) with no radiation and an image (FF) recorded with an open field irradiation. This calibration image, however requires a uniform FF image. To achieve uniformity, an optimum thickness of solid water buildup has to be found. The imager is calibrated with varing the thicknesses of a solid water builup placed on the detector surface. These calibrated images were compared to ionisation chamber recorded in water at dmax. The measurements assume lineaire proportionality between EPID and the dose deposed in the central axis. The portal imager a-Si1000 is characterized by good stability of the signal in a short time.

O36: ISOTOPIC CHARACTERIZATION FOR NUCLEAR REACTIONS IN THE OKLO NATURAL REACTORS

H. Hidaka¹, S. E. Bentridi², B. Gall³ and N. Amrani⁴

¹Department of Earth and Planetary Sciences, Nagoya University, Nagoya 464-8601, Japan

²Laboratoire de l’Energie et des Systèmes Intelligents, Université Djilali Bounaama Khemis Miliana, Algérie

³Institut Pluridisciplinaire Hubert Curien, 23 rue du Loess, Strasbourg

⁴Laboratory for Dosage and Analysis of Characteristic in height resolution (DAC)

Physics department, faculty of sciences, UFAS University, Algeria

Abstract

The Oklo uranium ore in the Francevillian basin at the east part of the Republic of Gabon is known as a fossil of natural fission reactors, because large-scaled fission chain reactions spontaneously occurred in the ore two billion years ago. It is of major concern to characterize the properties of nuclear reactors and to investigate the behavior of fission products in and around the Oklo natural reactors. In this review, geological and physico-chemical characteristics of the Oklo natural fission reactor and its implication for radioactive waste disposal are shown.

The Oklo uranium deposit had partly functioned as natural fission reactors.Large-scale fission chain reactions spontaneously occurred at 16 separate areas in the Oklo deposit, so-called “reactor zones (hereafter, RZs)”, two billion years ago, and sustained intermittently for 24000 to 300000 years.Since the main reactions in RZs are caused by ²³⁵U fission, significant depletion of ²³⁵U (²³⁵U/²³⁸U<0.007252) is observed in the RZs samples. The fission process for thermal neutron-induced ²³⁵U fission produces fragments with a wide range of mass (72<A<162; A=mass number), and neutrons. As the results, many elements of the Oklo RZs and the related samples show the variations in the isotopic compositions caused by a combination of nuclear fission, neutron capture and radioactive decay.Isotopic measurements by mass spectrometry provide useful information of geochemical behavior of fissiogenic radioisotopes and neutronic characteristics of the reactors. Since the discovery of the first RZ in 1972, many isotopic studies have been performed to understand the mechanism of the operation as fission reactors and to trace the migration behaviors of fissiogenic isotopes produced in the reactors.

Elements compatible with U, such as rare earth elements (REE) have been relatively well retained in the reactors in spite of weathered conditions in and around the RZs. On the contrary there are some differences in the retention of non-compatible elements between weathered and non-weathered reactors. Besides the properties of fissiogenic nuclides, the differences in degree of retention of fissiogenic nuclides between RZs may depend upon the hydrologic, thermal, mechanical and physicochemical conditions of the RZ. The retentivities of radionuclides produced in a RZ vary in different locations even in the same RZ.

The estimation of nuclear parameters of reactors is required to elucidate the fission mechanism in the natural fission reactors. Some of REE isotopes such as¹⁴³Nd,¹⁴⁹Sm,¹⁵⁵Gd and¹⁷⁶Lu sensitively interact with fission-released neutrons because of their large neutron capture cross-sections. Nuclear parameters of analyzed samples can be quantitatively calculated by using isotopic deviations of such nuclides.In this talk, some typical examples of the isotopic data from the Oklo RZs, and explain the interpretation will be shown.

O37: Generic Model For Natural Nuclear Reactors: From Oklo To A Possible Prior Georeactor

S. E. Bentridi^1,2, B. Gall², F. Gauthier-Lafaye³, N. Amrani⁴, H. Hidaka⁵, D. Benzaid¹, M. Guerrache⁴

¹ Laboratoire de l’Energie et des Systèmes Intelligents, U.D.B.K.M, Route de Theniet El-Hed 44225, Algérie.

²Institut Pluridisciplinaire Hubert Curien, UMR 7871, 23 rue du Loess 67037 Strasbourg, France.

³Laboratoire d’Hydrologie et de Géochimie de Strasbourg, 1 rue Blessig, 67084 Strasbourg, France.

⁴DAC Laboratory, Physics Department, Faculty of Sciences, Ferhat ABBAS University, Sétif 19000, Algeria

⁵ Department of Earth and Planetary Sciences, Nagoya University, Nagoya 464-8601, Japan

Abstract

The Oklo natural nuclear reactors (located in Franceville basin, Gabon) present a real case of long-life operating nuclear system with thermal neutrons. Without any possible human intervention and considering their geological history, Oklo reactors were always considered as the natural analogue of geological storage of nuclear waste. Under thermal effects, altered surroundings of reactor cores evolved into a clay envelope of this high U-rich ore. The key to understand the operating of Oklo reactors undergo the understanding of thermal effects besides the neutron physics of such a system. The modern and recent processing of historical drills and outcrops of Oklo situation shed light on some unrevealed feature on the way how nature acted to ignite and maintain a sustained chain of fission reactions. Initially, MCNPX simulations permit us to explore and investigate related neutron physics of Oklo situation with real geological constraints and limits. Later, with developed shell scripts dedicated to natural U-rich configurations it became possible to interact with Monte-Carlo simulations and optimize time and calculation power to define all possible critical configurations, even for different geological ages. We extrapolate then, from Oklo case to a generic model covering any possible natural nuclear fission reactors occurrence. Very small dimensions cylinder (about few centimeters radius by few tens centimeters length) could be obtained as possible critical configurations for an older age before 2.0 b.y. Here, nature made it in easier way with long life systems including waste management with fuel confinement in space and time. Probably, prior natural nuclear reactors to Oklo have been occurred in an ancient past but their confirmation needs more investigation and new way to observe their signatures, unlike the Oklo case which presents a physical presence with several observations, measurements and analysis

O38: Modern Point of view on Oklo

B. Gall¹, S. E. Bentridi^1,2, F. Gauthier-Lafaye³, H.Hidaka⁴

¹Institut Pluridisciplinaire Hubert Curien, UMR 7871, 23 rue du Loess 67037 Strasbourg, France.

²Laboratoire de l’Energie et des Systèmes Intelligents, U.D.B.K.M, Route de Theniet El-Hed 44225, Algérie.

³Laboratoire d’Hydrologie et de Géochimie de Strasbourg, 1 rue Blessig, 67084 Strasbourg, France.

⁴Department of Earth and Planetary Sciences, Nagoya University, Nagoya 464-8601, Japan

Abstract

The Oklo phenomenon discovered in a 2 billion years old uranium deposit remains a scientific mystery for 45 years since its discovery. A complete understanding of this phenomenon needs to associate neutron physics with geological statements. The occurrence of criticality of the Oklo reaction zones has been explained in previous works (NAUDET 1991, BENTRIDI 2011) but the questioning about how did those systems operate and evolve in their geological environment. Scientific studies were carried out by means of bore holes, geological cuts and outcrops made during the exploitation of the Oklo andOkelobondo mining sites. These sites are now drowned as are the neighboring sites of Mounana and Mikouloungou. In the site of Bangombé a reactor was identified in sub-surface. It is preserved for the collective memory after having been studied by a set of boreholes. We have recently compiled the historical geological information from Oklo using the GDM software from the BRGM. On the basis of 3D reconstruction of reaction zones 2 to 6, we were able to extract 2D projections and maps which revealed the characteristics of couplings of certain cores. The second part of the presentation will begin with the presentation of these unique data. Their precise analysis in terms of coupling and dynamics of the cores will then be discussed before concluding on a model of evolution of the cores running from the start of the first small cores to the advent of big cores such as the reactor 2 which mobilized several hundred tons of uranium.

O39: A SIMPLIFIED NUCLEAR THERMALHYDRAULIC CHANNEL MODEL FOR NUCLEAR RESEARCH REACTORS USING PLATE TYPE FUEL

K. Sidi Ali¹ and R. Salhi²

¹Nuclear Research Center of Draria, Algiers, Algeria

²ENPEI Rouiba, Algiers, Algeria

Abstract

The thermalhydraulic nuclear reactor core channel analysis is done thanks to the conservation equations of mass, momentum and energy, for an incompressible fluid. The conservation equation of momentum is solved upwards in the channel in order to obtain the velocity in the channel using Runge Kutta method of order 4 without the pressure term, knowing the inlet velocity which is taken as initial velocity. At the same time the differential pressure equation is solved downwards in the channel, by Euler method, using the outputs of the preceding calculation and using the output pressure as the initial value. When the entire values of velocity and pressure vectors are obtained, a loop calculation is carried out using the ascending Euler method for velocity and then descending for pressure until convergence. The power generated in the channel is evaluated using the indicated power of the installation weighted by a conversion efficiency factor and a factor giving the ratio of the flow in the channel and the total flow in the nuclear reactor core. The physical thermal quantities are then evaluated. The main results obtained deal with the evolution of the cooling fluid velocity and the static pressure along the thermalhydraulic channel as well as the evolution of the cooling fluid temperature and the temperature of the clad along this same channel. This approach is applied for a 02 MW nuclear research reactor using plate type fuel. The temperature profile of the coolant and the clad along the nuclear reactor core channel are plotted. For an upward flow, the obtained results were compared to those given by Boudali and Salhi, to those given by the code TERMIC and to those obtained by Labani et al.. The obtained results are very close to those obtained by the cited authors and the calculated relative differences are minor.

O40: NEUTRON DIFFRACTION ANALYSIS OF BaTi_1-xMg_x_/3Nb_2x/3O₃(x = 0.03) COMPOSITION

N. Bensemma¹, A. M. Venter², M. Salhi¹, Z. N. Sentsho², K. Taїbi³

¹ Nuclear Research Centre of Birine, BP 180, Djelfa, Algeria

² South African Nuclear Energy Corporation (NECSA) SOC Limited, PO Box 582, Pretoria 0001, South Africa

³ Crystallography and Thermodynamic, Chemistry Faculty, USTHB, Bab-Ezzouar, Algiers, Algeria

Abstract

In comparison with X-ray diffraction, Neutron powder diffraction, owing to its relatively higher scattering cross section for oxygen, is particularly useful in the detection of weak and high angle peaks in perovskite-type oxides, thus provide more accurate lattice parameters and allow for a more precise detection of any symmetry changes. Therefore, in this work Neutron diffraction data were used to study the structural features of the material Ba(Ti_(1-x)Mg_x_/3Nb_2x/3)O₃ with x=0.03.

Neutron powder diffraction data were collected at three temperatures T=300K, 260K and 200 K using the PITSI diffractometer at the Safari 1 Research Reactor (NECSA, South Africa). The 2θranges covered were 10– 115^º in 0.05552^º steps, and with λ=1:08 Å. Rietveld reﬁnement full profile fitting was done using the program FULLPROF (Rodriguez-Carvajal 1995).The following neutron scattering factors were used b_Ba = 5,071 fm, b_Ti= -3.438 fm, b_Mg =5.375 fm, b_Nb =7.054 fm and b_O =5.803 fm. The background was linearly interpolated between given points, taken from each proﬁle, while the peak shapes were modeled using a pseudo-Voigt proﬁle shape function. The evolution of structural parameters with temperature has been discussed.

O41: DETERMINATION OF RARE EARTH ELEMENT REE IN GEOLOGICAL MATERIAL BY NEUTRON ACTIVATION ANALYSIS INAA AND K₀-NAA

L. Hamidatou Alghem, K. Djebli

Neutron Activation Analysis laboratory, Nuclear Research Centre of Birine, Po Box 180, Ain Oussera, 17200, Algeria

Abstract

The mobilization of rare earth elements (REEs) in the environment requires monitoring of these elements in environmental matrices, in which they are mainly present at trace levels. The similarity in (REEs) chemical behavior makes the separate determination of each element by chemical method difficult; instrumental neutron activation analysis INAA and k₀-NAA, based on nuclear properties of these elements to be determined , is a method of choice in trace analysis of REEs and related elements. NAA was applied as a sensitive nondestructive analytical tool for the determination of RRE to find out what information could be obtained about the REE of Algerian red rock collected from Azzazgua in Tizi-ouzzou, north centre of Algeria.

The samples were properly prepared together with standards and flux monitors are simultaneously irradiated in a neutron flux of 4.77 10¹² n/cm²s at Es-Salam Resaerch reactor. The following elements have been determined : Ce, Eu, La, Lu, Nd, Sc, Sm, Tb et Yb. The gamma spectra were collected by HP-Ge detector operated with Genie 2k software and the deconvolution was done by means of HyperLab program. To evaluate the accurate of the results the CRM-GSD12 (sediment) and NIST -1646a was executed. The analytical results showed that the relative error of most of the elements was less than 10%.

O42: TRIAXIAL ROTOR MODEL WITH RIGID MOMENTS OF INERTIA

A. Bouldjedri

PRIMALAB Laboratory, Department of Physics, Batna 1 University, Algeria

Abstract

An alternative to the hydrodynamical triaxial rotor of Davydov and Filippov is investigated. In this approach I have adopted the nuclear moments of inertia resulting from the rigid nucleus approximation. The model is tested by comparing its predictions to the experimental data.

The triaxial rotor model has been introduced by Davydov and Filippov in 1958 as an analytic solution to Bohr Hamiltonian. The authors adopted an irrotational flow assumption to express the moments of inertia. The resulting model shows a symmetry about g=30° and a singular behavior for g=0° and g=60°.

In the present work the dependence upon the deformation (b, g) parameters is relaxed by adopting rigid moments of inertia. New expressions for the energy levels and transition probabilities are formulated.

In order to test the model two sets of the deformation parameters values are extracted using the energies and the decay properties, respectively. Subsequently, they are used to calculate the spectra and the transition probabilities of well deformed nuclei, mainly in the rare-earths region. The relevance of the model is then discussed.

O43: Energy absorption buildup factors and exposure buildup factors variations with depth for biological matrices in photon energies 0.05 to 3 MeV

H. H. Saleh¹, J.M. Sharaf²

¹: Al-Hussein Bin Talal University, Radiography Department, Ma'an, Jordan.

²: The University of Jordan, Department of Physics, Amman, Jordan

Corresponding author's email: hanhas2002@gmail.com; hanan_saleh@ahu.edu.jo.

Abstract

Radiation dose received by human biological matrices and the distribution of photon flux inside the body in any medical imaging or radiation therapy is affected by various parameters such as mass attenuation coefficients, equivalent atomic number and build up factors. Energy absorption (EABF) and exposure buildup factors (EBF) have been estimated for some biological matrices including nine different tissues in the energy region 0.05–3 MeV up to a penetration depth of 40 mfp (mean free path). Geometric progression (G-P) fitting approximation has been used to calculate EABF and EBF of adipose, skin, muscle, brain, blood, lung, soft, compact bone, and cortical bone tissues. It has been observed that the examined biological matrices show variations in their EABF and EBF with incident photon energy, penetration depth and equivalent atomic number with a significant difference in the intermediate region where Compton scattering dominates. The obtained buildup factor can be useful in estimation the biological effects of radiation doses.

O01: Parity Deduction from Cross Section Analysis of Isotopes of some Transuranium Elements

J. A. Bamikole1, M. N. Agu2 and P. O.Akusu2

O02: DOUBLE DIFFERENTIAL PROTON EMISSION CROSS SECTIONS FOR STRUCTURAL FUSION MATERIALS 24 Mg

G. Demirelli1*, I.H. Sarpun1, E. Tel2, A. Aydin3

O03: NEUTRON PRODUCTION CROSS–SECTION CALCULATIONS FOR SOME GAMMA AND PROTON INDUCED REACTIONS ON 89Y

A. Kaplan1, M. Şekerci1, B. Demir2

O04: DENSITY DEPENDENT NEW CROSS SECTION CALCULATIONS OF 10BORON TARGET NUCLEI

E. Tel1, I.H. Sarpun2, M. Sahan1, A. Aydin3, A. Bulbul1

O05: K-SHELL INTERNAL CONVERSION COEFFICIENT OF g-RAY TRANSITION IN Ba*137

J. Jose1,2, S. B. Gudennavar1*, L. Francis Maria Anand1,3 and S. G. Bubbly1

O06: STOPPING POWER OF PROTONS FOR ENERGIES AND MATERIALS OF THERAPEUTIC IMPORTANCE USING MONTE CARLO SIMULATIONS

A. Bozkurt1 and I. H. Sarpun2

O07: SHELL CLOSURE NUCLEI N = 82 STUDYING AND INTERPRETATION: CERIUM ISOTOPES 136-138CE

S. Kaim1 and A. Abboudi

O08: PRELIMINARY SURVEY OF ACTIVITY CONCENTRATION OF NORM IN SOIL SAMPLES FROM RICHARDS BAY, SOUTH AFRICA.

Felix B. Masok1 , Paulus L. Masiteng1, Risimati D. Mavunda2, Peane P. Maleka3, Hartmut Winkler4

O09: Radiolysis of pharmaceuticals in wastewater using irradiation technology

W. Jahouach-Rabai1,2, Z. Azzouz-Berriche2, R. Lahsni3,B. Habibi3, A. Ghrabi1

O10: INDUSTRIAL WASTEWATER TREATMENT USING HIGH ENERGY ELECTRON BEAM IRRADIATION: REMOVAL OF CHROMIUM (VI) HEAVY METAL

F. Djouider1 and M. S. Aljohani1

O11: MICROEXTRACTION OF URANIUM AND NUCLEAR FORENSIC ANALYSIS BY CHEMOMETRIC BASED LASER ABLATION MOLECULAR ISOTOPIC SPECTROSCOPY (LAMIS)

J. N. Malaba1, F.O. Oduor2, H. K. Angeyo3

O12: Uncertainty and Sensitivity analysis of LBLOCA transient in CALLISTO loop using SUSA code

A. Hadjam1, D. Saad2, H. Boucherit3, H. A. Kaliatka4,T. Kaliatka5, M. Valinčius6

O13: Interaction of a Gaussian laser beam with an acousto-optical cell

A.Benstiti1, K.Ferria1, A.Bencheikh1, 2

O14: UV-VIS SPECTROSCOPY OF Eu3+ AND Gd3+ IONS DOPED YPO4

S. Hachani1, L. Guerbous2, A. Zemiri3, K. Djelloul3

O15: NEMA NU-2 2012 PERFORMANCE EVALUATION OF THE FIRST PET-CT SYSTEM INSTALLED IN ALGERIA

A. Toutaoui, M. Belmessaoud, S. Bencheikh, R. Louelh

O16: Investigation of the initial and volume recombination losses in gamma versatile ionization chamber VGIC developed for gamma ray dosimetry

M.Fares1, S.Mameri1, M. Y. Debili2, A.Bouranane K.Negara

O17: THE DOSE RATE MEASUREMENTS OF C-ARM FLUOROSCOPIC X-RAY SYSTEMS WITH AND WITHOUT APRON

N. Tuncel1,2

O18: RADIATION TRANSMISSION THROUGH LAMINATED BARRIER FOR HIGH-ENERGY LINEAR ACCELERATORS USED IN RADIOTHERAPY

R. Bechchar and J. ghassoun1

O19: Photodynamic Therapy and cancers, current state and perspectives in Algeria

A. Oulhissane1, A. Baba Ahmed2

O20 : Large pixelated CZT versus conventional NaI(Tl) gamma camera

N. Boutaghane1, 2, B. Bouzid1, H. Zaidi3,4,5,6.

O21: LIGHT CHARGED PARTICLE EMISSION OF B4C COMPOSITES

I.H. Sarpun1, A. Bozkurt2, A. Aydin3, S. Pat4

022: K-SHELL JUMP FACTOR AND JUMP RATIO OF 3d ELEMENTS

L. Francis Maria Anand1,2, S. B. Gudennavar1*, S.G. Bubbly1, B. R. Kerur3 and L. D. Horakeri4

O23: Measurement of radon exhalation rate and natural radioactivity in the northern areas of Punjab, Pakistan

S. A. Mujahid, M. Akram and P.O. Nilore,

O24 : HEALTH HAZARDS RELATED TO URANIUM CONCENTRATION IN DRINKING WATER COLLECTED FROM NATURAL SPRINGS OF THE JHELUM VALLEY, AZAD KASHMIR – PAKISTAN

M. Akram1, A. Iqbal2, N. U. Khattak3, S. A. Mujahid, S. Hussain, M. U. Rajput, N. Zafar

O25: NEW METHOD FOR DETERMINATION OF REEs BY NEUTRON ACTIVATION ANALYSIS FOR SOIL REDISTRIBUTION STUDY

A. Azbouche1, M. Belamri1, M. Belgaid2,

O26: TRACE ELEMENTS INVESTIGATION AND QUALITY ASSESSMENT IN SOIL SAMPLES BY INAA

Z. Bouhila, A. Nedjar, T. Azli, D. Boukhadra, A. Hadri

O27: DEGRADATION MECHANISM OF A GLASS/UNSATURATED POLYESTER COMPOSITE EXPOSED TO GAMMA RADIATION

N. Belloul1, K. Boumerdassi1, B. Kouini1, A. Ahmed Benyahia2, D. Haouanoh3, A. Serier1

O28: EVALUATION AND OPTIMISATION OF TREATMENT PLANS USING RADIOBIOLOGICAL MODELS

O. D. Osahon1 and G. E. Okungbowa2

O29: INVESTIGATION OF CABLE INSULATOR RESISTANCE TO g-RAY AND NEUTRON IRRADIATION

M. Izerrouken1, Dj. Haddad1, S. Berkani1, T. Seguini1, R. Zamoun1, A. Ameur1, H. Zirour2

O30: Study of the Proton Irradiation Effect on the Performances of the GaAs Solar Cell

S. Tahar1 and A. Nouri2

O31: THERMAL HYDRAULIC TRANSIENT ANALYSISOF ACCIDENT SCENARIOFOR VVER440 USING APROS-6 COMPUTER CODE

Y. Bouaichaoui

O32: FREQUENCY OF DICENTRICS IN HUMAN BLOOD IRRADIATED IN VITRO

K. D. Aouragh, H. Amara-Hamai, M.K. Bach-Tobdji, A. Djefal-Kerrar and N. Ait Said

O33: PHYSICAL AND BIOLOGICAL EVALUATION OF 3D TREATMENT PLAN FOR PROSTATE CANCER

A. Boughalia1, M. Fellah2, S. Khoudri3, S. Haoui3, K. Boualga3

O34: LONG-TERM CONSEQUENCE ON KIDNEY AND LIVER ORGANS OF IODINE-131 CONTAMINATED WISTAR RATS (WITH AND WITHOUT THYROID)

M. Mezaguer-Lekouaghet1, A. Badreddine1, S. Mameri2, M. Souidi3, A. Baz4& Z. Lounis-Mokrani1

O35: Development of calibration procedures of an Electronic Portal Imaging Devices a-Si 1000 used for IMRT and VMAT

A. Maachou1, A. Toutaoui2, N.Khelassi-Toutaoui1, R. Louelh2, Z.Sakhri-Brahimi1 and A. C. Chami3

O36: ISOTOPIC CHARACTERIZATION FOR NUCLEAR REACTIONS IN THE OKLO NATURAL REACTORS

H. Hidaka1, S. E. Bentridi2, B. Gall3 and N. Amrani4

O37: Generic Model For Natural Nuclear Reactors: From Oklo To A Possible Prior Georeactor

S. E. Bentridi1,2, B. Gall2, F. Gauthier-Lafaye3, N. Amrani4, H. Hidaka5, D. Benzaid1, M. Guerrache4

O38: Modern Point of view on Oklo

B. Gall1, S. E. Bentridi1,2, F. Gauthier-Lafaye3, H.Hidaka4

O39: A SIMPLIFIED NUCLEAR THERMALHYDRAULIC CHANNEL MODEL FOR NUCLEAR RESEARCH REACTORS USING PLATE TYPE FUEL

K. Sidi Ali1 and R. Salhi2

O40: NEUTRON DIFFRACTION ANALYSIS OF BaTi1-xMgx/3Nb2x/3 O3 (x = 0.03) COMPOSITION

N. Bensemma1, A. M. Venter2, M. Salhi1, Z. N. Sentsho2, K. Taїbi3

J. A. Bamikole¹, M. N. Agu² and P. O.Akusu²

O02: DOUBLE DIFFERENTIAL PROTON EMISSION CROSS SECTIONS FOR STRUCTURAL FUSION MATERIALS ²⁴ Mg

G. Demirelli^1*, I.H. Sarpun¹, E. Tel², A. Aydin³

O03: NEUTRON PRODUCTION CROSS–SECTION CALCULATIONS FOR SOME GAMMA AND PROTON INDUCED REACTIONS ON ⁸⁹Y

A. Kaplan¹, M. Şekerci¹, B. Demir²

O04: DENSITY DEPENDENT NEW CROSS SECTION CALCULATIONS OF ¹⁰BORON TARGET NUCLEI

E. Tel¹, I.H. Sarpun², M. Sahan¹, A. Aydin³, A. Bulbul¹

O05: K-SHELL INTERNAL CONVERSION COEFFICIENT OF g-RAY TRANSITION IN Ba^*137

J. Jose^1,2, S. B. Gudennavar¹^*, L. Francis Maria Anand^1,3 and S. G. Bubbly¹

A. Bozkurt¹ and I. H. Sarpun²

O07: SHELL CLOSURE NUCLEI N = 82 STUDYING AND INTERPRETATION: CERIUM ISOTOPES ^136-138CE

S. Kaim¹ and A. Abboudi

Felix B. Masok¹ , Paulus L. Masiteng¹, Risimati D. Mavunda², Peane P. Maleka³, Hartmut Winkler⁴

W. Jahouach-Rabai¹^,2, Z. Azzouz-Berriche², R. Lahsni³,B. Habibi³, A. Ghrabi¹

F. Djouider¹ and M. S. Aljohani¹

J. N. Malaba¹, F.O. Oduor², H. K. Angeyo³

A. Hadjam¹, D. Saad², H. Boucherit³, H. A. Kaliatka⁴,T. Kaliatka⁵, M. Valinčius⁶

A.Benstiti¹, K.Ferria¹, A.Bencheikh^1,
2

O14: UV-VIS SPECTROSCOPY OF Eu³⁺ AND Gd³⁺ IONS DOPED YPO₄

S. Hachani¹, L. Guerbous², A. Zemiri³, K. Djelloul³

M.Fares¹, S.Mameri¹, M. Y. Debili², A.Bouranane K.Negara

N. Tuncel^1,2

R. Bechchar and J. ghassoun¹

A. Oulhissane¹, A. Baba Ahmed²

N. Boutaghane¹^{, 2}, B. Bouzid¹, H. Zaidi^3,4,5,6.

O21: LIGHT CHARGED PARTICLE EMISSION OF B₄C COMPOSITES

I.H. Sarpun¹, A. Bozkurt², A. Aydin³, S. Pat⁴

L. Francis Maria Anand^1,2, S. B. Gudennavar^1*, S.G. Bubbly¹, B. R. Kerur³ and L. D. Horakeri⁴

M. Akram¹, A. Iqbal², N. U. Khattak³, S. A. Mujahid, S. Hussain, M. U. Rajput, N. Zafar

A. Azbouche¹, M. Belamri¹, M. Belgaid²,

N. Belloul¹, K. Boumerdassi¹, B. Kouini¹, A. Ahmed Benyahia², D. Haouanoh³, A. Serier¹

O. D. Osahon¹ and G. E. Okungbowa²

M. Izerrouken¹, Dj. Haddad¹, S. Berkani¹, T. Seguini¹, R. Zamoun¹, A. Ameur¹, H. Zirour²

S. Tahar¹ and A. Nouri²

A. Boughalia¹, M. Fellah², S. Khoudri³, S. Haoui³, K. Boualga³

M. Mezaguer-Lekouaghet¹, A. Badreddine¹, S. Mameri², M. Souidi³, A. Baz⁴& Z. Lounis-Mokrani¹

A. Maachou¹, A. Toutaoui², N.Khelassi-Toutaoui¹, R. Louelh², Z.Sakhri-Brahimi¹ and A. C. Chami³

H. Hidaka¹, S. E. Bentridi², B. Gall³ and N. Amrani⁴

S. E. Bentridi^1,2, B. Gall², F. Gauthier-Lafaye³, N. Amrani⁴, H. Hidaka⁵, D. Benzaid¹, M. Guerrache⁴

B. Gall¹, S. E. Bentridi^1,2, F. Gauthier-Lafaye³, H.Hidaka⁴

K. Sidi Ali¹ and R. Salhi²

O40: NEUTRON DIFFRACTION ANALYSIS OF BaTi_1-xMg_x_/3Nb_2x/3O₃(x = 0.03) COMPOSITION

N. Bensemma¹, A. M. Venter², M. Salhi¹, Z. N. Sentsho², K. Taїbi³

O41: DETERMINATION OF RARE EARTH ELEMENT REE IN GEOLOGICAL MATERIAL BY NEUTRON ACTIVATION ANALYSIS INAA AND K₀-NAA

H. H. Saleh¹, J.M. Sharaf²