Nuclear Science and Technology Research Institute
Journal of Nuclear Science and Technology (JONSAT)
1735-1871
2676-5861
31
2
2010
08
23
Study on a HF Measurement Procedure at Chemical Traps Output of Uranium Enrichment Facilities, under Medium Vacuum
1
6
FA
K
Karimpour
گروه مهندسی شیمی، دانشکده فنی، دانشگاه تهران، صندوق پستی: 4563-11365، تهران ـ ایران
S.J
Safdari
پژوهشکده چرخه سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران ـ ایران
jsafdari@aeoi.org.ir
M.A
Mousavian
گروه مهندسی شیمی، دانشکده فنی، دانشگاه تهران، صندوق پستی: 4563-11365، تهران ـ ایران
<span style="font-family: Times New Roman; font-size: small;">The flow passed chemical traps is a mixture of light gas, hydrogen fluoride and uranium hexafluoride. It is necessary to take samples from the chemical traps output flow, to assure the accurate operation, non-saturation of adsorbent, proper loading and to control the output concentration of hydrogen fluoride and uranium hexafluoride. The routine approach for sampling is impossible because of the process of continuity and vacuum conditions. A procedure for the chemical traps output sampling is introduced in this paper under the assumption of the lack of uranium hexafluoride at the output of the chemical trap, and its effective parameter was optimized. As a result, the sampling time and pressure which are considered as the most important parameter were evaluated and their optimized values were estimated.</span>
Chemical Trap,Sampling,Vacuum,Hydrogen fluoride
https://jonsat.nstri.ir/article_446.html
https://jonsat.nstri.ir/article_446_99c4d7cfa83bf0d4ee729eaecdf3979b.pdf
Nuclear Science and Technology Research Institute
Journal of Nuclear Science and Technology (JONSAT)
1735-1871
2676-5861
31
2
2010
08
23
Mathematical Modeling and Performance Analysis of a Rotary Reactor
Used for UO2 Production
7
22
FA
J
Moshayyedi
دانشکده فنی و مهندسی، واحد علوم و تحقیقات، دانشگاه آزاد اسلامی، صندوق پستی: 775-14155، تهران- ایران
A
Rahimi
دانشکده مهندسی، دانشگاه اصفهان، صندوق پستی: 73441-81746، اصفهان ـ ایران
G.R
Jahanfarnia
دانشکده فنی و مهندسی، واحد علوم و تحقیقات، دانشگاه آزاد اسلامی، صندوق پستی: 775-14155، تهران- ایران
In the present study the rotary reactor used for producing UO<sub>2 </sub>from AUC is modeled. For this purpose, the governing equations, including mass and energy balance equations for the existing species and phases are derived based on the conservation laws and then they were solved numerically. All other required parameters for solving the governing equations, including the geometrical characteristics of the solid bed, hydrodynamic conditions of the bed and reactor, thermo-physical properties of gaseous and solid species and existing reactions were obtained from the literature and were used. Individual reaction kinetics, presented in the literature for the reactions which are taking place in this reactor, shows many shortages for condition in which all the reactions are taking into account simultaneously. Thus, for the first time, a new kinetics model is proposed and is applied successfuly. The results of using the model are in good agreement with the logical and expected behavior which can be obtained based on the principles of chemical engineering science.
UO2,AUC,Rotary Reactor,Modeling,Kinetics Model
https://jonsat.nstri.ir/article_447.html
https://jonsat.nstri.ir/article_447_33aea6f24ffb1d997c02e6b7c6c79ff6.pdf
Nuclear Science and Technology Research Institute
Journal of Nuclear Science and Technology (JONSAT)
1735-1871
2676-5861
31
2
2010
08
23
Construction and Development of a Chemical Dosimeter Based on the Radiochromic Solid Polymer and Evaluation of it’s Response to High Energy Photons Used in Radiotherapy
23
29
FA
A
Mostaar
گروه فیزیک پزشکی، دانشکده علوم پزشکی، دانشگاه تربیت مدرس، صندوق پستی: 151-14115، تهران- ایران
B
Hashemi
گروه فیزیک پزشکی، دانشکده علوم پزشکی، دانشگاه تربیت مدرس، صندوق پستی: 151-14115، تهران- ایران
bhashemi@modares.ac.ir
M.H
Zahmatkesh
انستیتو پرتو پزشکی نوین، صندوق پستی: 1466643691، تهران- ایران
M.R
Aghamiri
گروه پرتو پزشکی، دانشکده علوم هستهای، دانشگاه شهید بهشتی، صندوق پستی: 1983963113، تهران- ایران
S.R
Mahdavi
گروه فیزیک پزشکی، دانشکده پزشکی، دانشگاه علوم پزشکی ایران، صندوق پستی: 141555983، تهران- ایران
<span style="font-family: Times New Roman;">Recent advances in radiation therapy have made obvious the need for dosimeters that can measure three-dimensional (3-D) dose distributions. Currently, radiosensitive gel dosimeters have provided 3-D dose measurements using the MRI technique. However, this method has some limitations. Recently, a novel transparent polymer dosimeter, PRESAGE, has been introduced which exhibits a radiochromic response when exposed to ionizing radiation. This dosimetry technique has some advantages compared with other gel dosimeters. In this study, the dose response, linearity, sensitivity, and stability of this type of dosimeter were investigated for different levels of the activator, and leuco dye concentration. In this regard, the PRESAGE dosimeters were made with different formulations and were irradiated by gamma-rays of Cobalt-60 in the dose range of 0-50 Gy. Then, the optical absorption changes of the dosimeters were measured by a spectrophotometer over a period of 14 days after the irradiation. The results indicated that increasing the activator concentration leads to the increase of the sensitivity, but decreases the stability of the dosimeter response. Furthermore, it was noted that the dosimeter shows a linear response to the radiation dose with a high level of correlation (R<sup>2</sup>>0.99)<span style="font-size: small;">.</span></span>
<span style="font-family: Times New Roman;"> </span>
Radiotherapy,Radiation Dosimetry,Radiochromic Polymer,Sensitivity,Stability,Linearity
https://jonsat.nstri.ir/article_448.html
https://jonsat.nstri.ir/article_448_ef37ae60054774bf46fc3373e9462347.pdf
Nuclear Science and Technology Research Institute
Journal of Nuclear Science and Technology (JONSAT)
1735-1871
2676-5861
31
2
2010
08
23
Sorption of Metal Ions on Synthetic Organoinorganic Ion Exchanger Polyacrylonitril-Ti(IV) Tungstophosphate
30
39
FA
A
Heidary
شرکت پسمانداری صنعت هستهای ایران، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران ـ ایراندانشکده شیمی، دانشگاه آزاد اسلامی واحد تهران شمال، صندوق پستی: 1913674711، تهران- ایران
S.J
Ahmadi
پژوهشکده چرخه سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران ـ ایران
M.R
Asadi
پژوهشکده علوم هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 3486-11365، تهران ـ ایران
F
Asgharizadeh
پژوهشکده چرخه سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران ـ ایران
P
Ashtari
پژوهشکده چرخه سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران ـ ایران
pashtari@aeoi.org.ir
<span style="font-family: Times New Roman;"><span style="font-size: small;">In this study two Polyacrylonitril-Ti(IV) tungstophosphate organo-inorganic ion exchangers with different molar ratios have been synthesized. </span><span style="font-size: small;">These ion exchangers have been characterized </span></span><span style="font-family: Times New Roman;"><span style="font-size: small;">by </span><span style="font-size: small;"> FT-IR, X- ray diffraction, TG, SEM and CHNSO techniques and their cation exchange capacity has been measured by continuous method.</span><span style="font-size: small;"> Distribution coefficients (K</span><sub><span style="font-size: small;">d</span></sub><span style="font-size: small;">) for metal ions and radionuclides were determined by batch method and</span></span><span style="font-family: Times New Roman;"><span style="font-size: small;">with these ion exchangers, separation of metal ions was achieved on a glass column</span><span style="font-size: small;">.</span></span>
Ion Exchanger,Polyacrylonitrile-Ti(IV) Tungstophosphate,Metal Ions,Cation Exchange Capacity,Separation,Batch Method,Distribution Coefficient
https://jonsat.nstri.ir/article_449.html
https://jonsat.nstri.ir/article_449_cf3afc16d64eae7c8cfc4468a1a2da93.pdf
Nuclear Science and Technology Research Institute
Journal of Nuclear Science and Technology (JONSAT)
1735-1871
2676-5861
31
2
2010
08
23
Production, Quality Control and Biological Evaluation of 90Y-EDTMP in Rats
40
43
FA
R
Adeli
1- دانشکده مهندسی هستهای و فیزیک، دانشگاه صنعتی امیرکبیر، صندوق پستی: 4413-15875، تهران ـ ایران
M
Ghannadi Maragheh
0000-0002-3370-1810
1- دانشکده مهندسی هستهای و فیزیک، دانشگاه صنعتی امیرکبیر، صندوق پستی: 4413-15875، تهران ـ ایران2- پژوهشکده چرخه سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران ـ ایران
mghanadi@aeoi.org.ir
M
Shamsaei Zafarghandi
دانشکده مهندسی هستهای و فیزیک، دانشگاه صنعتی امیرکبیر، صندوق پستی: 4413-15875، تهران ـ ایران
A
Bahrami Samani
دانشکده مهندسی هستهای و فیزیک، دانشگاه صنعتی امیرکبیر، صندوق پستی: 4413-15875، تهران ـ ایران2- پژوهشکده چرخه سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران ـ ایران
B
Salimi
2- پژوهشکده چرخه سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران ـ ایران
b.salimi@aeoi.org.ir
Pain palliation of bone metastases is one of the perspectives of medical science. Among the different modalities, the use of radionuclides is a well-established approach. One of these radionuclides is Yttrium-90 (<sup>90</sup>Y) associated with chemical component EDTMP. One method for production of <sup>90</sup>Y is neutron activation of <sup>89</sup>Y. This radionuclide is a pure beta emitter with a high energy and appropriate half life and has been considered for medical usages in nuclear medicine. In this research <sup>90</sup>Y has been produced by irradiation of Y<sub>2</sub>O<sub>3</sub> powder and by the addition of EDTMP ligand, the <sup>90</sup>Y-EDTMP complex has been achieved at ambient temperature. Radiochemical purity was investigated by ITLC method and radionuclidic purity by liquid scintillation counting. The radiopharmaceutical biodistributions were performed in different rat organs.
Bone metastases,Yttrium-90,EDTMP,Radiopharmaceutical,Biodistribution
https://jonsat.nstri.ir/article_450.html
https://jonsat.nstri.ir/article_450_5d52a559ea8c92f2253259b1893ec8c7.pdf
Nuclear Science and Technology Research Institute
Journal of Nuclear Science and Technology (JONSAT)
1735-1871
2676-5861
31
2
2010
08
23
Gamma Radiation Effects on Bacterial Contamination and Organoleptic Characteristics of Frozen Ponaeus Monodon
44
48
FA
F
Motamedi Sedeh
پژوهشکده تحقیقات کشاورزی، پزشکی و صنعتی، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 498-31485، کرج- ایران
R
Afsharian
اداره کل دامپزشکی استان هرمزگان، صندوق پستی: 1799-79145، بندرعباس- ایران
H.R
Zolfagarieh
پژوهشکده تحقیقات کشاورزی، پزشکی و صنعتی، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 498-31485، کرج- ایران
M
Nikbakht
اداره کل دامپزشکی استان هرمزگان، صندوق پستی: 1799-79145، بندرعباس- ایران
S.K
Shafaee
پژوهشکده تحقیقات کشاورزی، پزشکی و صنعتی، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 498-31485، کرج- ایران
M
Ayazi
اداره کل دامپزشکی استان هرمزگان، صندوق پستی: 1799-79145، بندرعباس- ایران
H
Fatolahi
پژوهشکده تحقیقات کشاورزی، پزشکی و صنعتی، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 498-31485، کرج- ایران
A
Moharami
پژوهشکده تحقیقات کشاورزی، پزشکی و صنعتی، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 498-31485، کرج- ایران
M
Babaee
پژوهشکده تحقیقات کشاورزی، پزشکی و صنعتی، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 498-31485، کرج- ایران
The aim of this study was the application of irradiation process to decrease bacterial contamination of the penaeus monodon. The shrimp samples were obtained from Hormozgan and were sent to the microbiological laboratory. Bacterial contamination of shrimp were determined by counting the aerobic mesophil bacteria, Staphylococcus areus, Choliforms, Vibrio parahemolyticus and Salmonella. The shrimp samples were irradiated at different doses of gamma ray. Finally, the optimum dose of the gamma ray for bacterial decontamination of shrimp, especially of Vibrio Parahemolyticus, was obtained to be 2kGy. Also, the chemical factors of irradiated and non-irradiated samples such as Protein, Fat, total volatile Nitrogen (TVN), Non Protein Nitrogen (NPN), Peroxide Value (PV) and Amino Acids were measured. There were not any important difference among them. Also, there were not any significant difference between TVN and Peroxide Value (P>0.05) for the irradiated and <br /> non-irradiated shrimp samples. Study of bacterial contaminations of the irradiated and non irradiated samples after 12 months showed that irradiation by 2kGy can control the microbial contaminations. Four types of films for packaging: Pet.pe, Pp.pe, Bopp, and Pe.20 were used for storage of the irradiated and non irradiated shrimp samples in-18°C during 12 months. All of the packages were studied on the aspects of color, odor, tissue and taste of shrimp samples and elasticity and pressing of packages. For the irradiated and non irradiated shrimp Pet.pe and Pp.pe were preferred, respectively.
Shrimp,Bacterial Contamination,Gamma radiation,Packaging
https://jonsat.nstri.ir/article_451.html
https://jonsat.nstri.ir/article_451_e0a07ba9655d61c30364ec32787935b8.pdf
Nuclear Science and Technology Research Institute
Journal of Nuclear Science and Technology (JONSAT)
1735-1871
2676-5861
31
2
2010
08
23
Uranium Ore Pre-Treatment with Gravity Separation in Saghand Ore Deposit
44
48
FA
S
Alamdar Milani
پژوهشکده چرخه سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران ـ ایران
salamdar@aeoi.org.ir
H
Hamidian
دانشکده فنی و مهندسی، دانشگاه آزاد اسلامی واحد علوم و تحقیقات، صندوق پستی: 775-14155، تهران- ایران
<span style="font-family: Times New Roman;"><span style="font-size: small;">The low grade mineral needs pre-treatment operation prior to concluding processing. This is especially proper for uranium and gold mineral naturally forming low grade into crest of the earth. This paper surveyes the enhancement of uranium ore grade in Saghand by using gravity separations methods. The mineral deposits grade is low and refractory within this realm. The study of mineralization demonstrated that uranium ore type is Davidite and the average content of the uranium specified by </span><span style="font-size: small;"> X-ray diffraction analysis was 300ppm. Also, the amount of other minerals were 57.39% (SiO</span><sub><span style="font-size: small;">2</span></sub><span style="font-size: small;">), 1.29% (TiO</span><sub><span style="font-size: small;">2</span></sub><span style="font-size: small;">), 5.64% (Fe</span><sub><span style="font-size: small;">2</span></sub><span style="font-size: small;">O</span><sub><span style="font-size: small;">3</span></sub><span style="font-size: small;">) and the contented value of rare earth elements, as well. The initial step of processing operation is to release the elements, particularly uranium. Therefore, the ore sample is crushed by jaw and roll crusher and then ground by rod milling to gain access to suitable degree of liberation. The milling output size was classified by the laboratory screens and divided into six sections. Each section of the screened product was washed by water and separated by shaking table. The results confirmed an increase in the grade of uranium and other minerals up to 4463ppm</span><span style="font-size: small;">.</span></span>
Pretreatment,Degree of Liberation,Gravity Separation,Uranium,Saghand
https://jonsat.nstri.ir/article_452.html
https://jonsat.nstri.ir/article_452_71bba1f213d40759f88a72a3d20f98ef.pdf
Nuclear Science and Technology Research Institute
Journal of Nuclear Science and Technology (JONSAT)
1735-1871
2676-5861
31
2
2010
08
23
Investigation of Molybdenum Content Reduction in Uranium Leach Liquor by Using Activated Charcoal in Bandar Abbas Plant
54
59
FA
A
Ghadiri
گروه پژوهشی اکتشاف و استخراج، پژوهشکده چرخه سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران ـ ایران
N
Nozari
گروه پژوهشی اکتشاف و استخراج، پژوهشکده چرخه سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران ـ ایران
Sh
Moghtaderi
گروه پژوهشی اکتشاف و استخراج، پژوهشکده چرخه سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران ـ ایران
In this work, the possibilities of molybdenum content reduction in uranium leach liquor was investigated by adsorption techniques. Several activated charcoals were used as adsorbents. Under the optimized condition, 83.59% of molybdenum was adsorbed with “Norit PK 0.25-1” activated charcoal. Since the low uranium adsorption is the aim of this work, by performing the optimization conditions, the uranium adsorption with activated charcoal was determined to be 2.74%.
Activated Charcoal,Molybdenum,Leach Liquor,Uranium
https://jonsat.nstri.ir/article_453.html
https://jonsat.nstri.ir/article_453_610674aea2ebe60abe5e3dc71be78ccf.pdf
Nuclear Science and Technology Research Institute
Journal of Nuclear Science and Technology (JONSAT)
1735-1871
2676-5861
31
2
2010
08
23
Dose Rate Calculation of Radiation Emitted from 30B Cylinder Containing Natural UF6
60
66
FA
M
Vafabakhsh
پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 1339-14155، تهران- ایران
A
Rahimi
پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 1339-14155، تهران- ایران
arahimy@aeoi.org.ir
A.H
Taherizadeh Saghand
پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 1339-14155، تهران- ایران
H
Havasi
پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 1339-14155، تهران- ایران
<span style="font-family: Times New Roman;"><span style="font-size: small;">D</span>ose rate is one of the most important factors that should be considered in handling, stacking and transportation of nuclear materials for the occupational radiation protection and for the people who are exposing to. Uranium hexafluoride is one of the radioactive compounds of uranium which is used in the enrichment industry. UF<sub>6</sub> is kept and transferred in special carbon steel containers. In this study, the absorbed dose of radiations emitted from 30B cylinder containing fully-aged natural UF<sub>6</sub> is simulated by MCNP4C code and results are compared with the actual data. The absorbed dose rate depends on some factors such as cylinder contents, storage time before and after discharge, radiation energy, geometry, the enrichment percent, etc. The satisfactory consistency between the calculations and measurements confirms that the simulation model can contribute to the dose mapping data around the UF<sub>6</sub> cylinder and can be used for determination of the allowable exposure time and to control absorbed dose rate. This study is performed experimentally at the KALA ELECTRIC Company<span style="font-size: small;">.</span></span>
MCNP,Dose Rate,Radioactivity,Uranium hexafluoride,UF6 Cylinder
https://jonsat.nstri.ir/article_454.html
https://jonsat.nstri.ir/article_454_6d1f5e44f45043500f654fe15700ad1b.pdf
Nuclear Science and Technology Research Institute
Journal of Nuclear Science and Technology (JONSAT)
1735-1871
2676-5861
31
2
2010
08
23
Optimization of [67Ga]-Oxinate Complex Formation Conditions for white Blood Cell Labeling
67
71
FA
A.R
Jalilian
پژوهشکده تحقیقات کشاورزی، پزشکی و صنعتی، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 498-31485، کرج- ایران
A
Vakilli
دانشکده فنی و مهندسی، دانشگاه آزاد اسلامی واحد علوم و تحقیقات، صندوق پستی: 775-14515، تهران - ایران
S
Nazari
دانشکده فنی و مهندسی، دانشگاه آزاد اسلامی واحد علوم و تحقیقات، صندوق پستی: 775-14515، تهران - ایران
F
Bolourinovin
پژوهشکده تحقیقات کشاورزی، پزشکی و صنعتی، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 498-31485، کرج- ایران
bolorinovin@yahoo.com
S
Rajabifar
0000-0002-6479-3252
پژوهشکده تحقیقات کشاورزی، پزشکی و صنعتی، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 498-31485، کرج- ایران
srajabifar1958@gmail.com
In this work, the effective factors on the preparation of <sup>67</sup>Ga-oxinate complex for white blood cell labeling were determined. Gallium-67 was produced at AMIRS 30MeV cyclotron via <sup>68</sup>Zn(p,2n)<sup>67</sup>Ga reaction in the from of <sup>67</sup>GaCl<sub>3</sub>, and was used for radiolabeling of oxinate complex at optimized conditions. A mixture of <sup>67</sup>GaCl<sub>3 </sub>(3uL, 200uCi) and ethanolic oxine solution (1mg/ml, 100μl) was evaporated and reacted at 25<sup>º</sup>C for 1 h in the presence of NaOAc solution (pH. 5.5). ITLC was performed using a mixture of ammonium actetae and methanol solution (1:1) followed by recording the activity using radio thin layer chromatography scanner. The radiochemical purity of %95.18 at these conditions was obtained (specific activity of 1432 GBq/mmol). Freshly prepared white blood cells were separated from human volunteers and used for labeling by the above mentioned complex at 37<sup>º</sup>C. <sup>67</sup>Ga-oxinate complex due to it’s lipophilicity and suitable gamma rays is a suitable cell labeling agent and available for blood stem cell and microorganism studies.
Gallium-67,Oxinate Complex,Optimization,Cell Labeling
https://jonsat.nstri.ir/article_455.html
https://jonsat.nstri.ir/article_455_d96350252584147a43169e8547a048d8.pdf
Nuclear Science and Technology Research Institute
Journal of Nuclear Science and Technology (JONSAT)
1735-1871
2676-5861
31
2
2010
08
23
Discernment of Irradiated Chicken Meat by Determination of O-Tyrosine Using High Performance Liquid Chromatography and Fluorescence Detection
72
79
FA
F
Aflaki
پژوهشکده علوم هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 3486-11365، تهران ـ ایران
A
Roozbahani
پژوهشکده علوم هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 3486-11365، تهران ـ ایران
ali_roozbahani2003@yahoo.com
M
Salahinejad
پژوهشکده علوم هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 3486-11365، تهران ـ ایران
<span style="font-size: small;"><span style="font-family: Times New Roman;">O-Tyrosine is proposed as a marker for identification of irradiated protein-rich foods. In this study, HPLC/ Fluorescence method that allows accurate quantification of 0.1ng of o-tyrosine has been used. The method involves freeze-drying of sample, acid hydrolysis and fractionation by HPLC. By using Spherisorb ODS2 column, the base-line separation of o-tyrosine from impurities was performed. The yield of o-tyrosine in the irradiated chicken meat was proportional to the irradiation dose. Since the variable levels of o-tyrosine were found in unirradiated chicken meat (0.15-0.42 µg/g per wet weight), this method is able to identify the irradiated chicken meat at 4kGy or higher. Because the dose response curve can be extended over 50kGy, the method is suitable for detecting the overdosed samples.</span></span>
O-Tyrosine,Irradiated Food,Detection,High Performance Liquid Chromatography
https://jonsat.nstri.ir/article_456.html
https://jonsat.nstri.ir/article_456_756da5744f878ad73ae9da4eeccda2be.pdf
Nuclear Science and Technology Research Institute
Journal of Nuclear Science and Technology (JONSAT)
1735-1871
2676-5861
31
2
2010
08
23
Nuclear Radiations Induced Change in Thermal and Structural Properties of
2-}[4-(2-HydroxyBenzylideneamino) Phenylimino] Methyl{ Phenol (PAM) Schiff Base
80
86
FA
H.G.
Mohammadi
Department of Physics, Faculty of Science, Urmia University, P.O. Box: , Urmia- Iran
R.
Khodabakhsh
Department of Physics, Faculty of Science, Urmia University, P.O. Box: , Urmia- Iran
A.
Hassanzadeh
2- Department of Chemistry, Faculty of Science, Urmia University, P.O. Box: , Urmia- Iran
3- Research Center of Nanotechnology of Urmia University, P.O. Box: , Urmia- Iran
The variation of thermal and structural properties of 2-{[4-(2-hydroxybenzylideneamino) phenylimino]methyl}phenol (PAM)Schiff base were studied using differential scanning calorimetry (DSC) and powder X-ray diffraction techniques before and after fast neutron (1.050 and 1.740kGy), beta (11.01Gy) and gamma (453.0Gy) irradiations. Under fast neutron irradiation, the melting and decomposition enthalpies and temperatures were changed with increasing the irradiation time. The kinetic parameters were calculated using both model free isoconversional and Kissinger analysis methods. Gamma irradiation showed similar effectonstructural and thermal properties.
Schiff Base,Model- Free Isoconversional Method,Kissinger Analysis Method,Fast Neutron,Beta,Gamma Irradiations
https://jonsat.nstri.ir/article_457.html
https://jonsat.nstri.ir/article_457_d44c27db0d0f1da07de7eb2e0c01d0b5.pdf