ORIGINAL_ARTICLE
Preliminary Investigation on Designing and Developing 90Sr/90Y Generator for Nuclear Medicine Purposes
Yttrium-90 radioisotope as a daughter of Strontium-90 is one of the nuclear fission products and plays an important role in the treatment of malignant tumors in nuclear medicine. There are at least five methods for the separation of Y-90 from Sr-90 including: Liquid membrane separation, Precipitation solvent extraction ion exchange and solvent extraction combined with ion exchange method. In this work ion exchange chromatography was used by Dowex50Wx8 resin as a stationary phase and ammonium oxalate, EDTA and sodium Acetate solutions as mobile phases. Separation of yttrium and strontium was performed in the various simulation conditions and for determining the elements, ICP-AES technique was used. The activities of real samples were estimated with β-liquid scintillation counter. The various shielding parameters for designing different parts of generator were also considered in this work.
https://jonsat.nstri.ir/article_516_205d11b8acd8e56d80abaa91d29b3bdb.pdf
2009-02-19
1
9
90Sr/ 90Y Generator
90Sr and 90Y Separation
Ion Exchange Chromatography
Nuclear Medicine
Strontium-90
Yttrium-90
Radioisotope Generators
M.H
Mojarrabi Tabrizi
1
پژوهشکده چرخه سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران- ایران
AUTHOR
A
Khanchi
akhanchi@aeoi.org.ir
2
پژوهشکده چرخه سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران- ایران
LEAD_AUTHOR
M
Firouz Zare
mfirooz@aeoi.org.ir
3
پژوهشکده چرخه سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران- ایران
AUTHOR
B
Salimi
b.salimi@aeoi.org.ir
4
پژوهشکده چرخه سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران- ایران
AUTHOR
M
Deilami
5
پژوهشکده چرخه سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران- ایران
AUTHOR
A
Amrollah Abhari
6
پژوهشکده چرخه سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران- ایران
AUTHOR
1. S.Y. Adelstein and F.J. Manning, (Editors), “Isotopes for medicine and the life sciences,” National Academies press (1995).
1
2. “Nuclear Medicine Resources Manual,” IAEA, International Atomic Energy Agency, printed by the IAEA in Austria (2006).
2
3. P.J. Ell and S.S Gambhir, (Editors), “Nuclear medicine in clinical diagnosis and treatment (Vol.182) 3rd,” Churchill Livingstone (Elsevier Limited) (2004).
3
4. M. Venkatesh, U. Pandey, P.S. Dhami, R. Kannan, P.V. Achutan, R.R. Chitnis, V. Gopalakrishnan, S. Baneryee, G. Samual, M.R.A. Pillai, A. Ramanujam, “Complexation studies with 90Y from a Novel 90Sr-90Y Generator,” Radiochim Acta 89, 413 (2001).
4
5. U. Pandey, A. Mukheryee, H.D. Sharma, T. Das, M.R.I. Pillai, M. Venka Tesh, “Evaluation of 90Y-DTPA and 90Y-DOTA for potential application in intra-vascular radionuclide therapy,” Appl. Radiat. Isot. 57, 313 (2002).
5
6. U. Pandey, A. Mukherjee, H.D. Sharma, T. Das, M.R.A. Pillai, M. Venkatesh, “Preparation and studies with 90Y-labelled particles for use in radiation synovectomy,” Appl. Radiat. Isot. 55, 471 (2001).
6
7. A. Mukherjee, U. Pandey, H.D. Sharma, M.R.A. Pillai, M. Venkatesh, “Preparation and evaluation of 90Y skin patches for therapy of superficial tumours in mice,” Nucl. Med. Comm. 23, 243 (2002).
7
8. Edgardo Browne and Richard B. Firestone Virginias Shirley, “Table of radioactive isotopes,” U.S.A, P:90.1-90.6, Edition: 2, )1986(.
8
9. Z. Graheh, I. Eskinja, K. Kosutic, S. Cerjan-Stefanovic, “Isolation of yttrium and strontium from soil samples and rapid determination of 90Sr,” J.Croatica Chemica Acta (CCACAA), 73(3), 795-807 (2000).
9
10. A. Gran Malonda, L. Rodriguez Barquero, A. Grau Carles, “Radioactivity determination of Y-90, Sr-90 and Sr-89 mixtures by spectral deconvolution,” Nucl. Instr. Meth. Phys. Res. A339, 31-37 (1994).
10
11. Develoment of Generator Technologies for Therapeutic Radionuclides, (1stResearch Coordination Meeting),” IAEA Headqarters Vienna, Austria, 4-8 October (2004).
11
12. Y.J. Koda, “Separation of pure 90Y from a 90Sr-90Y mixture by co-precipitation with ferric hydroxide,” Inorg. Nucl. Chem. 25, 733 (1963).
12
13. M.L. Salutsky and H.W. Kirby, “Preparation and half life of carrier-free Yttrium-90,” Anal. Chem. 27(4), 567-569 (1955).
13
14. H.L. Volchok and J.L. Kulp, “Half-life of Yttrium-90,” Phys. Rev. 97, 102 (1955).
14
15. J.S. Wike, C.E. Guyer, D.W. Ramey, B.P. Pillips, “Chemistry for commercial scale production of yttrium-90 for medical research,” J. Radiat. Appl. Instrum. Part A, 41, No. 9, 861 (1990).
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16. R.F. Doering, W.D. Tucker, L.G.Jr. Stang, Report BNL-5454 (1962).
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17. V.G. Herrmann and F. Strassmann, “Concerning the search for Sr and y isotopes from U fission,” Z. Nautrforsch, 11A, 946 (1956).
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18. K. Seyb and G.Z. Herrmann, Elektrochem. 64, 1065 (1960).
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19. E. Minami, M. Honda, Y. Sasaki, “Ion-exchange separation of fission products,” Bull, Chem. Soc. Japan. 31, 372 (1958).
19
20. Y. Suzuki, “Preparation of carrier-free 90Y from 90Sr with ion exchange,” Journal. Appl. Radiation & Isotopes, 15, 599-602 (1964(.
20
21. A.T. Rane and K.S. Bhatki “Rapid radiochemical separations of strontium-90-yttrium-90 and calcium-45-scandium-46 on a cation exchange resin,” Anal. Chem. 38, 1598-1601 (1966).
21
22. W.Y. Skraba, H. Arino, H.H. Kramer, “A new 90Sr/90Y radioisotope generator,” J. Appl. Radio & Isotope. 29, 91 (1978).
22
23. M. Chinol and D.J. Hnatowich, “Generator produced yttrium-90 for radioimmunotherapy,” J. Nucl. Medicine, 28, 1465 (1987).
23
24. S. Misumi and T.J. Taketatsu, “Separation of yttrium-90 from strontium-90 and lanthanum-140 from barium-140 with anion exchange, resin of carbonate form,” Inorg. Nucl. Chem. 20, 127 (1961).
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25. R.W. Perkins, “Filtration-precipitation separation of barium-140 from lanthanum-140,” Anal. Chem. 29(1), 152-153 (1957).
25
26. P. Sylvester, US. Patent applications No. 2003/0231994 and 2004/0005272.
26
27. N.D. Betenekov, L.M. Sharygin, R.W. Brown, “90Sr/90Y radionuclide generator for production of high-quality Y-90 solution,” US. Patent. 7101484, September (2006).
27
28. H. Cember, “Introduction to Health Physics,” 4th.ed )2008(.
28
ORIGINAL_ARTICLE
Radiolabeling Quality Control and Biodistribution Study of Anti-CD20 Antibody by 67Ga
Nowadays, anti-CD20 antibodies are being used in the therapy of lymphomas in free or radiolabeled form. Conjugation process was performed using native antibody and DOTA-NHS compound, synthesized in our laboratory. Thin layer chromatography and gel filtration were used to control the reaction progress as well as purification of the final antibody conjugate. 67GaCl3 produced at AMIRS was used to label the immunoconjugate and the reaction conditions were optimized for time, temperature and reactant concentrations. Quality control of the radioimmunoconjugate was performed using RTLC and gel filtration. The radiochemical purity was shown to be over 95%. The radioimmunoconjugate was used in the biodistribution studies up to 28 h and it was shown that after 24h most of the activity was accumulated in reticuloendothelial system consisting liver and spleen.
https://jonsat.nstri.ir/article_517_ca98b3b924b45af163b0bd62eb34eb43.pdf
2009-02-19
10
17
Anti-CD20
DOTA
67Ga
Rituximab
Cyclotron
Quality Control
Biodistribution
Labeling
Radioisotope production
A.R
Jalilian
1
پژوهشکده تحقیقات کشاورزی، پزشکی و صنعتی، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 498-31485، کرج- ایران
LEAD_AUTHOR
L
Mirsadeghi
2
گروه بیولوژی، دانشگاه پیام نور، ناحیه 10، تهران ـ ایران
AUTHOR
A
Khorrami
3
1- پژوهشکده تحقیقات کشاورزی، پزشکی و صنعتی، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 498-31485، کرج- ایران
AUTHOR
S
Moradkhani
smoradkhani@nrcam.org
4
1- پژوهشکده تحقیقات کشاورزی، پزشکی و صنعتی، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 498-31485، کرج- ایران
AUTHOR
B
Naserian
5
1- پژوهشکده تحقیقات کشاورزی، پزشکی و صنعتی، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 498-31485، کرج- ایران
AUTHOR
S
Daneshvari
6
1- پژوهشکده تحقیقات کشاورزی، پزشکی و صنعتی، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 498-31485، کرج- ایران
AUTHOR
N
Shadanpour
7
1- پژوهشکده تحقیقات کشاورزی، پزشکی و صنعتی، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 498-31485، کرج- ایران
AUTHOR
H
Ghahreman
8
1- پژوهشکده تحقیقات کشاورزی، پزشکی و صنعتی، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 498-31485، کرج- ایران
AUTHOR
R
Haji-Hosseini
9
گروه بیولوژی، دانشگاه پیام نور، ناحیه 10، تهران ـ ایران
AUTHOR
1. T.E. Witzig, C.A. White, G.A. Wiseman, L.I. Gordon, C. Emmanouilides, A. Raubitschek, N. Janakiraman, J. Gutheil, R.J. Schilder, S. Spies, D.H. Silverman, E. Parker, A.J. Grillo-Lopez, “Phase I/II trial of IDEC-Y2B8 radioimmunotherapy for treatment of relapsed or refractory CD20(+) B-cell non-Hodgkin's lymphoma,” J. Clin. Oncol. 17, 3793–3803 (1999).
1
2. J.F. Eary, O.W. Press, C.C. Badger, L.D. Durack, K.Y. Richter, S.J. Addison, K.A. Krohn, D.R. Fisher, B.A. Porter, D.L. Williams DL, et al, “Imaging and treatment of B-cell lymphoma,” J. Nucl. Med. 31, 1257–1268 (1990).
2
3. S.J. Knox, R. Levy, R.A. Miller, W. Uhland, J. Schiele, W. Ruehl, R. Finston, P. Day-Lollini, M.L. Goris, “Determinants of the antitumor effect of radiolabeled monoclonal antibodies,” Cancer Res. 50, 4935-4940 (1990).
3
4. R.A. Kyle, M.A. Gertz, P.R. Greipp, T.E. Witzig, J.A. Lust, M.Q. Lacy, T.M. Therneau, “Long-term survival (10 years or more) in 30 patients with primary amyloidosis,” Blood, 93(3), 1062-1066 (1999).
4
5. M. Dietlein, H. Pels, H. Schulz, O. Staak, P. Borchmann, K. Schomäcker, T. Fischer, W. Eschner, E.P. von Strandmann, H. Schicha, A. Engert, R. Schnell, “Imaging of central nervous system lymphomas with iodine-123 labeled rituximab,” Eur. J. Haematol. 74, 348-352 (2005).
5
6. J. Hoffend, W. Mier, J. Schuhmacher, K. Schmidt, A. Dimitrakopoulou-Strauss, L.G. Strauss, M.E.R. Kinscherf, U. Haberkorna, “Gallium-68-DOTA-albumin as a PET blood-pool marker: experimental evaluation in vivo,” Nucl. Med. Biol. 32, 287–292 (2005).
6
7. O. Ugur, P.J. Kothari, R.D. Finn, P. Zanzonico, S. Ruan, I. Guenther, H.R. Maecke, S.M. Larson, “Ga-66 labeled somatostatin analogue DOTA-DPhe1-Tyr3-octreotide as a potential agent for positron emission tomography imaging and receptor mediated internal radiotherapy of somatostatin receptor positive tumors,” Nucl. Med. Biol. 29, 147–157 (2002).
7
8. M.R. McDevitt, D.Ma,J. Simon, R.K. Frank, D.A. Scheinberg, “Design and synthesis of 225Ac radioimmun opharmaceuticals,” Applied Radiat. Isot. 57, 841–847 (2002).
8
9. C.J. Smith, H. Gali, G.L. Sieckman, D.L. Hayes, N.K. Owen, D.G. Mazuru, W.A. Volkert, T.J. Hoffman, “Radiochemical investigations of 177Lu-DOTA-8-Aoc-BBN[7-14] NH2: an in vitro/in vivo assessment of the targeting ability of this new radiopharmaceutical for PC-3 human prostate cancer cells,” Nucl. Med. Biol. 30, 101–109 (2003).
9
10. L.L. Chappell, E. Dadachova, D.E. Milenic, K. Garmestani, C.Wu, M.W. Brechbiel, “Synthesis, Characterization, and Evaluation of a Novel Bifunctional Chelating Agent for the Lead Isotopes 203Pb and 212Pb,” Nucl. Med. & Biol. 27, 93–100 (2000).
10
11. S. Banerjee, T. Das, S. Chakraborty, G. Samuel, A. Korde, S. Srivastava, M. Venkatesha, M.R.A. Pillai, “177Lu-DOTA-lanreotide: A novel tracer as a targeted agent for tumor therapy,” Nucl. Med. Biol. 31, 753–759 (2004).
11
12. W. Mier, J. Hoffend, S. Kramer, J. Schuhmacher, W.E. Hull, M. Eisenhut, “Conjugation of DOTA using isolated phenolic active esters: The labeling and biodistribution of albumin as a blood-pool marker,” Bioconjug. Chem. 16, 237–240 (2005).
12
13. U. Pandey, A. Mukherjee, H.D. Sarma, T. Das, M.R.A. Pillai, M. Venkatesh, “Evaluation of 90Y-DTPA and 90Y-DOTA for potential application in intra-vascular radionuclide therapy,” Appl. Rad. Isot. 57, 313-318 (2002).
13
14. P. Goethals, M. Coene, G. Slegers, D. Vogelaers, J. Everaert, I. Lemahieu, F. Colardyn, G.R. Heyndrickx, “Production of carrier-free 66Ga and labeling of antimyosin antibody for positron imaging of acute myocardial infarction,” Eur. J. Nucl. Med. 16, 237-240 (1990).
14
15. J. Kowalski, M. Henze, J. Schuhmacher, H.R. Macke, M. Hofmann, U. Haberkorn. “Evaluation of positron emission tomography imaging using [68Ga]-DOTA-D Phe(1)-Tyr(3)-Octreotide in comparison to [111In]-DTPAOC SPECT. First results in patients with neuroendocrine tumors,” Mol. Imaging Biol. 5(1), 42-48 (2003).
15
16. U.K. Laemmli, “Cleavage of structural proteins during assembly of the head of the bacteriophage T4,” Nature (London),227, 680–685 (1970).
16
ORIGINAL_ARTICLE
The Study of Ionic Strength Effect on Stability Constant of Dioxouranium(VI) Complexes with Asparagine
In this study, the stability constant of dioxouranium with asparagine complexes and protonation constant of asparagine at different ionic strength was investigated. Measurements have been performed at 25°C, pH<3.5 and at ionic strengths ranging from 0.1 to 1.0 mol dm-3 sodium perchlorate, using combination of potentiometric and spectrophotometric techniques. The composition of the formed complexes and their stability constants were determined by cruve fitting method and it was shown that dioxouranium forms two mononuclear 1:1 and 1:2 species in the form of UO2(HL)2+ and UO2(HL)22+. The overall analysis of the present and the previous data dealing with the determination of stability constant at different ionic strength allowed us to obtain a general equation by which the formation constant determined at a fixed ionic strength can be calculated with a good approximation.
https://jonsat.nstri.ir/article_519_47187ad0deae46c0620e600ba1dc72ce.pdf
2009-02-19
18
24
Stability Constant
Ionic Strength
Dioxouranium (VI)
Asparagine
Spectrophotometry Potentiometry
M
Amiri
1
پژوهشکده علوم هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 3486-11365، تهران-ایران 1- گروه شیمی، دانشکده علوم، دانشگاه شهید بهشتی، صندوق پستی: 1213-45695، تهران-ایران
LEAD_AUTHOR
M
Rabbani
2
پژوهشکده علوم هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 3486-11365، تهران-ایران
AUTHOR
F
Gharib
3
1- گروه شیمی، دانشکده علوم، دانشگاه شهید بهشتی، صندوق پستی: 1213-45695، تهران-ایران
AUTHOR
M
Tahernejad Javazm
4
پژوهشکده علوم هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 3486-11365، تهران-ایران
AUTHOR
1. U. Casellato, P.A. Vigato, M. Vidali, “Actinide complexes with carboxylic acid Coord,” Chem.Rev. 26-85 (1987).
1
2. I. Grenhe, J. Fuger, R.J.M. Konings, R.J. Lemire, A.B. Muller, H. Wanner, “Chemical Thermodynamics of Uranium,” Elsevier Science Publishers (1992).
2
3. A.L. Lehninger, “Biochemistry worth publishers inc,” New York (1975).
3
4. M.T. Beck and I. Nagypal, “Chemistry of complex equilibria,” Halsted Press, New York (1990).
4
5. L.E. Orgel, “An introduction to transition metal chemistry,” John Wiley, NewYork (1960).
5
6. D. Langmuir, “Aqueous environmental geochemistry,” Prentice Hall, Upper Saddle River (1997).
6
7. V.M. Lobo, “Handbook of electrolyte solutions,” Elsevier, Amsterdam (1989).
7
8. W. Stumm and J.J. Morgan, “Aquatic Chemistry: Chemical Equilibria and Rates in Natural Waters,” (1995).
8
9. R.J. Motekaitis and A.E. Maratell, “The determination and use of stability constant,” Weinheim, New York (1992).
9
10. P.W. Atkin and A.K. Holker, “Ions in solutions,” Clarendo Press, Oxford, 86-90 (1972).
10
11. P.G. Daniele, C. Rigano, S. Sammartano, “Talanta,” 32,1 (1985).
11
12. R.C. Tewariand and M.N. Srivastava, “Talanta,” (1973).
12
13. “Talanta,” Vol. 20, pp.360-361, pergamon Press (1973).
13
14. F. Gharib, K. Zare, R. Cheraghali, “Russ. J. Inorg. Chem. 49, 6 (2004).
14
15. F. Crea, A. De Robertis, S. Sammartano, Ann Chim, 93(12): 1027-35 (2003).
15
16. H.L. Girdhar, Shamar Parveen, M.K. Puri, “Department of chemistry,” The university of Kashmir, Srinagar (1976).
16
17. A. Raghavan and M. Santappa, Curr. Sci. 39, 302 (1970).
17
ORIGINAL_ARTICLE
Sensitivity Analysis of Neutron Cross Section for Graphite and Lead by Using MCNP Code and Experimental Data
Because of the importance of safety in a nuclear system, nuclear data which are used in neutronic reactors design must be in a good accuracy. So examination and enhancement of nuclear data are of great importance. The aim of this work is to investigate the neutron cross section with carbon and lead and consequently improving them. In a research program conducted at the Isfahan Production and Research Center, blocks of lead and graphite were used. In the core of lead and carbon blocks, we placed an Am-Be source and then measured the flux of neutron outside of the assembly. The flux distribution was also calculated theoretically by MCNP code and the results were compared with the experiment. Comparison of the computation and the experimental results showed that the carbon sensitivity coefficients in the range of energies lower than 1MeV are negligible, while for the higher energies, especially between 5 to 6 MeV, these coefficients are nearly 5 percent. Also, lead sensitivity coefficients was varied from 0.2 to 0.67 for different energies. Finally, with the help of defining sensitivity coefficients, the values of cross section were varied. By using more advanced equipment for fast neutron detection, we are able to find better results in the other range of energy groups.
https://jonsat.nstri.ir/article_520_bcb1609cdd32664dcd87c0c4f3596c4c.pdf
2009-02-19
25
32
Neutron Sources
Cross Sections
Neutron Flux
Nuclear Data Collections
Sensitivity Analysis
Monte Carlo Method
MeV Range
A
Parvazian
1
دانشکده فیزیک، دانشگاه صنعتی اصفهان، صندوق پستی: 83111-84156، اصفهان - ایران
LEAD_AUTHOR
M
Sadeghi
2
مرکز تحقیقات و تولید سوخت هستهای اصفهان، صندوق پستی: 83111-84156، اصفهان- ایران
AUTHOR
1. C.E. Burgart, “Capabilities of morse multigroup monte carlo code in solving reactor eigenvalue problems,” December (1971).
1
2. P.M. Song, M.Z. Youssef, M.A. Abdou, “A new approach and computational algorithm for sensitivity/ uncertainty analysis for SED and SAD with application to beryllium integral experiment,” Nucl. Sci. Eng. 113-339 (1993).
2
3. H.B. Choi, T.J. Downar, “Sensitivity theory for the closed nuclear fuel cycle,” Nucl. Sci, Eng. 111-205 (1992).
3
4. M.Z. Yossef, W. Conn, C.W. Maynard, “Impact of cross-section uncertainties on the nuclear design,” Nucl. Technol. Fusion, 2 (1982).
4
5. C.R. Weisbin, C.M. Oblow, J.H. Marable, R.W. Peele, J.L. Lucius, “Application of sensitivity and uncertainty methodology to fast reactor integral experiment analysis,” Nuc. Sci. Eng. 66-307 (1978).
5
6. D.G Cacusi, “Global optimization and sensitivity analysis,” Nucl. Sci. Eng. 104-78 (1990).
6
7. “MCNP4C monte carlo N-Particle transport code system,” Los Alamos National Laboratory, April (2000).
7
8. M.E. Dunn, P.B. Fox, N.M. Greene, L.M. Petrie, “ENDF/B-VI library generation and testing for the scale code system,” Oak Ridge Tennessee,USA (2005).
8
ORIGINAL_ARTICLE
Stream-Sediment Geochemical Exploration for Uranium in Narigan Area Central Iran
Uranium deposits of Iran occur mainly in the Central Iran zone. Several uranium deposits have been discovered in this zone. The Narigan area is one of the most important uranium mineralized area in this zone. The uranium bearing sequences in this area are contained in the plutonic to volcanic rocks of Narigan which intruded to the Pre-Cambrian pyroclastics rocks. Plutonic and volcanic rocks are granite, ryolite and volcanoclastic. Diabasic dykes have been intruded to these igneous rocks. The plutonic and volcanic rocks have been covered by Cretaceous limestons which seem to be youngest the rocks in this area. The aim of our project is to develop a regional exploration strategy for uranium in these igneous rocks. A grid-based sampling was planned following the results of the previous geochemical mapping at a scale of 1:100,000, integrated with geophysical data and alteration zones and outcrop of intrusive rocks. The following results are based on geological, and stream geochemical explorations in 1:20000 scale of this area. During this study 121 samples were collected from the stream sediments of <80 mesh for final sampling. Ten percent of the samples were used for checking laboratories errors. The samples were collected according to conventional methods from 30-40 cm depth of stream sediments. Finally, geochemical and radiometric data were combined and the results introduced 3 anomalies in the Narigan area.
https://jonsat.nstri.ir/article_522_283c9c165057e948d750ccba3e95e95e.pdf
2009-02-19
33
42
Stream-Sediment Geochemical Exploration
Uranium
Narigan
Central Iran
M
Yazdi
m-yazdi@sbu.ac.ir
1
دانشکده علوم زمین، دانشگاه شهید بهشتی، صندوق پستی: 4716-19396، تهران - ایران
LEAD_AUTHOR
Kh
Khoshnoodi
khoshnoodi78@gmail.com
2
دانشکده علوم زمین، دانشگاه شهید بهشتی، صندوق پستی: 4716-19396، تهران - ایران
AUTHOR
M
Kavand
mdkavand@yahoo.com
3
پژوهشکده چرخه سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 1113-143995، تهران- ایران
AUTHOR
A
Ashteyani
4
پژوهشکده چرخه سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 1113-143995، تهران- ایران
AUTHOR
1. B.A. Samani, “Recognition of uraniferous provinces from the Precambrian of Iran,” Krystalinkum, vol. 19, 147-165 (1998).
1
2. ش. نوریان، ”مطالعه زمینشناسی اقتصادی و هالههای ژئوشیمیایی در حاشیه توده گرانیتی ناریگان،“ پایاننامه کارشناسی ارشد، دانشگاه تبریز (1378).
2
3
3. ح. جلیلیان، ”بررسی پترولوژی و پتروگرافی گرانیت ناریگان،“ پایاننامه کارشناسی ارشد، دانشگاه آزاد واحد تهران شمال (1379).
4
4. J. Ramezani and R.D. Tucker, “The saghand region, central Iran: U-Pb geochronology, petrogenesis and implications for Gondwana tectonics,” American Journal of Science, 303, 622-665 (2003).
5
5. ز. نوریان، ”ژئوشیمی کانیشناسی و ژنز اورانیوم در محدوده چاه جوله، ایران مرکزی،“ پایاننامه کارشناسی ارشد، دانشگاه شهید بهشتی، غیر چاپ شده (1387).
6
6. خ. خشنودی، ”اکتشافات ژئوشیمیایی رسوبات آبراههای و بررسی کانیسازی اورانیوم در حاشیه گرانیت ناریگان یزد،“ پایاننامه کارشناسی ارشد، دانشگاه شهید بهشتی، غیر چاپ شده (1386).
7
7. م. یزدی، ”روشهای مرسوم در اکتشافات ژئوشیمیایی،“ انتشارات دانشگاه شهید بهشتی، 148 صفحه (1381).
8
8. L.G. Boyle, “Geochemical prospecting for thorium and uranium deposits,” Elsevier Scientific Publicatios, 500 (1982).
9
9. F.J. Dahlkamp, “Uranium ore deposits,” Springer–Verlg. 449 (1993).
10
10. W.K. Fletcher, “Analytical methods in geochemical prospecting, handbook of exploration geochemistry (10),” Elsevier, Amsterdam. Vol.1, 184-206 (1981).
11
11. M. Hale and J.A. Plant, “Drinage geochemistry in mineral exploration,” Elsevier, Sci.Ltd., 120 (1994) .
12
12. F. Mrna, J. Cadek, D. Pavlu, “Methods of geochemical prospecting,” Geological survey Prague, 256 (1979).
13
13. ر. کوهی، م.ه. هادیزاده یزدی، ”اندازهگیری و آشکارسازی تابشهای هستهای،“ ناشر کتابستان مشهد، ترجمه (1371).
14
14. م. یزدی، خ. خشنودی، ”کانسارهای اورانیوم گرمابی،“ انتشارات سازمان انرژی اتمی ایران، ترجمه،280 صفحه (1386).
15
ORIGINAL_ARTICLE
Production and Labeling of Rhenium-186 and 188 via HEDP Using Natural Rhenium and it’s Biodistribution in Rats
In this project, production of radioactive rhenium for medical application by the Tehran Research Reactor, using natural rhenium along with labeling Rhenium by hydroxy ethiliden diphosphonate(HEDP) was investigated. After the production of Re-HEDP, its biodistribution in rats was also evaluated. To obtain the radioactive isotopes, natural rhenium with %99.9 purity, manufactured by Merck, was irradiated by the Tehran Research Reactor. Natural rhenium consists of two isotopes, Re-185 and Re-187, so irradiation the target with neutron in the reactor eventuates in two radioisotopes,186Re and 188Re. This research was performed in three phases. At the first phase, rhenium was irradiated in various irradiation boxes. The best result was 470mCi/mg after 5 days of irradiation. The chemical process includes oxidation of Re which in the presence of water results in formation of perhenic acid. Afterward, labeling of HEDP by means of Re is performed. All the process was performed in Lead Cell. Gamma spectroscopy and Thin Layer Chromatography were used for radionuclide and radiochemical purity, respectively. Re-HEDP was injected in rats and the biodistribution in different organs were studied by means of gamma spectroscopy. The results of the gamma spectroscopy approved the radionuclide purity. Labeling via HEDP resulted in %97.57 radiochemical purity. Biodistribution in rats showed (1.007 %ID/g 4h P.I), (0.89%ID/g 24h P.I) and (0.58 %ID/g 48h P.I) for bone and was the maximum percent of the absorbed dose rate.
https://jonsat.nstri.ir/article_523_bf56b8545948d7bc100b98f5cc212232.pdf
2009-02-19
43
49
Radiopharmaceutical
Rhenium 186 and Rhenium 188
Lebeling
HEDP (Hydroxy ethilidene diphoshponate)
Tissus Distribution
L
Moghaddam-Banaem
moghaddam.leila@gmail.com
1
دانشکده مهندسی هستهای و فیزیک، دانشگاه صنعتی امیرکبیر، صندوق پستی: 4413-15875، تهران-ایران
LEAD_AUTHOR
S
Setayeshi
setayesh@aut.ac.ir
2
دانشکده مهندسی هستهای و فیزیک، دانشگاه صنعتی امیرکبیر، صندوق پستی: 4413-15875، تهران-ایران
AUTHOR
M
Ghannadi
mghanadi@aeoi.org.ir
3
1- دانشکده مهندسی هستهای و فیزیک، دانشگاه صنعتی امیرکبیر، صندوق پستی: 4413-15875، تهران-ایران 2- گروه پژوهشی شیمی، پژوهشکده علوم هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 836-14893، تهران- ایران
AUTHOR
S.J
Ahmadi
4
2- گروه پژوهشی شیمی، پژوهشکده علوم هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 836-14893، تهران- ایران
AUTHOR
R
Gholipour
5
2- گروه پژوهشی شیمی، پژوهشکده علوم هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 836-14893، تهران- ایران
AUTHOR
M.A
Firouz zareh
6
گروه پژوهشی شیمی، پژوهشکده علوم هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 836-14893، تهران- ایران
AUTHOR
S.M
Mazidi
7
بخش رادیوایزوتوپ، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 1113-143995، تهران-ایران
AUTHOR
S.H
Mirfalah
8
بخش رادیوایزوتوپ، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 1113-143995، تهران-ایران
AUTHOR
1. K. Hashimoto, K. Yoshihara, “Rhenium Complexes Labeled with 186,188Re for Nuclear Medicine,” Topics in current Chemistry, V. 176 (1996).
1
2. K. Liepe, R. Hliscs, J. Kropp, R. Runge, F.F. Knapp, W.G. Franke, “Dosimetry of 188Re-Hydroxyethylidene Diphosphonate in Human Prostate Cancer Skeletal Metastases,” The journal of Nuclear Medicine, V.44, No. 6, June (2003).
2
3. J. Gaudiano, E. Savio, A. Paolino, “Relationship of Bone Uptake to radiation Doses in Bone Pain Treatment with 188Re-HEDP,” IAEA-CN-96/67P (1996).
3
4. F.F. Knapp, J. Pinkert, J. Kropp, W.Y. Lin, S.Y. Wang, “Rhenium Radioisotopes for Therapeutic Radiopharmaceuticals Development,” IAEA-TECDOC, 59-66, January (1999).
4
5. DCE Ng, MBBS, MRCP, FAMS, “Radioimmunotherapy: Brief Overview,” Biomedical Imaging and Intervention Journal, V.2(3) (2006).
5
6. V.J. Lewington, “Cancer Therapy Using Bone-Seeking Isotopes,” Phys. Med. Biol. V.41, 2027-2042 (1996).
6
7. Neeta Pandit-Taskar, M. Batraki, C.H. Divgi, “Radiopharmaceutical Therapy for Palliation of Bone Pain from Osseos Matastases,” Journal of Nuclear Medicine, V. 45, No. 8, August (2004).
7
8. K. Ogawa, T. Mukari, Y. Arano, A. Otaka, M. Ueda, T. Uehara, Y. Magata, K. Hashimoto, H. Saji, “Rhenium-186-Monoaminemonoamidedithiol-Conjugated Bisphosphonate Derivative For Bone Pain Palliation,” Nuclear medicine and Biology Journal, V. 33, 513-520 (2006).
8
9. Lin Uei-Tyng, Chu Chein-Hau, Hsieh Bor-Tsung, Hwang Wen-Song, “Dose evaluation and measurement of the 188Re liquid-filled balloon in intravascular brachytherapy,” Applied Radiation and Isotopes , V.61, 1323-1333 (2004).
9
10. L. Solin, V.A. Jakovlev, I.E. Alekseev, V.V. Lazarev, “Cyclotron Yields of Rhenium-186,” Medimond, 131-136 (2005).
10
11. R.A. Kuznetsov, C. Daming, A.N. Pakhomov, S.I. Klimov, Y. Honwei, C. Benzhu, “188W/188Re Generator Of 1 Ci Activity,” Medimond, F425R0025, 55-62 (2005).
11
12. G. Pfennig, H. Klewe-Nebenius, W. Seelmann-Eggebert, “Chart of the nuclides,” Markdienste Haberbeck GmbH, ISBN 3-921879-18-3 (1998).
12
13. R. Sayare, M. Ghannadi Maragheh, M. Shamsaie, “Theoretical calculations for the production of 99Mo using natural uranium in Iran,” Annals of Nuclear Energy, V.30, 883-895 (2003).
13
14. IAEA-TECDOC-1340 , “Manual for reactor produced radioisotopes,” January (2003).
14
15. H.R. Maxon, L.E. Schroder, L.C. Washburn, S.R. Thomas, R.C. Samaratunga, D. Biniakiewicz, J.S. Moulton, D. Cummings, G. Ehrhardt, V. Morris, “Rhenium-188(Sn)HEDP for Treatment of Osseous Metastases,” The Journal of Nuclear Medicine, V. 39, No. 4 (1998).
15
16. W.Y. Lin, C.P. Ling, S.J. Yeh, B.T. Hsieh, Z.T. Tsai, G. Ting, T.C. Yen, S.J. Wang, F.F. Knapp Jr, M.G. Stabin, “Rhenium-188 HEDP: a new generator-produced radiotherapeutic drug of potential value for the treatment of bone metastases,” European journal of Nuclear Medicine and molecular Imaging,V. 24 No. 6, June (1997).
16
17. G.S. Limouris, S.K. Skukla, “Gastric uptake during Re-186 HEDP bone scintigraphy,” Anticancer-Res. V.17, No. 3B, 1779-1781 (1997).
17
ORIGINAL_ARTICLE
Study on UF6 Gas Flow by Using Orifice and Needle Valve Under Medium Vacuum Condition and Investigation of Effective Parameters on It
In nuclear facility, the enrichment operation usually is carreid out under the medium and high vacuum conditions. Measurement of UF6 gas flow rate in the form of feed or product and tail is one of the principal parameters in operation and production. In this facility, several orifices were used to measure UF6 gas flow rate in the range of 10-80 gr/hr. Due to low pressure and mass flow range, measurement of flow rate should be made accurately. In this research, the method of flow rate measurement in tubes by using orifice and needle valve, and also effective parameters on it, has been studied. For the study of the gas flow rates, several orifices with different diameters were used. We observed that for a defined orifice diameter, an increase in the input pressure causes an increase in the flow rate and at a constant flow rate an increase in the input pressure causes a decrease in the orifice diameter. As the pressure difference between the upside and downside of the orifice increases, the flow rate will rise up to a certain limit. Since in all experiments of the needle valve, the ratio of outlet to the inlet pressure is less than 0.5926, the linearity of the mass flow change versus the inlet pressure at a constant cross sectional area shown to be consistant with the chock current equation. Also, the investigation of mass flow rates, when the valve is open, indicates that variations of the mass flow rate will increase against the inlet pressure and the pressure difference, intensively.
https://jonsat.nstri.ir/article_524_0dacc56946cc64a041cc8c9833cece5b.pdf
2009-02-19
50
58
Gas Flow
Orifice
Needle Valve
Medium Vacuum Condition
Flow Rate
Pressure Drop
Flowmeters
Z
Vatani
1
دانشکده مهندسی شیمی، دانشکده فنی، دانشگاه تهران، صندوق پستی: 4536-11365، تهران ـ ایران
LEAD_AUTHOR
S.J
Safdari
jsafdari@aeoi.org.ir
2
پژوهشکده علوم هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 1339-14155، تهران - ایران
AUTHOR
H
Abolghasemi
hoab@ut.ac.ir
3
دانشکده مهندسی شیمی، دانشکده فنی، دانشگاه تهران، صندوق پستی: 4536-11365، تهران ـ ایران
AUTHOR
R
Orouj
4
دانشکده مهندسی شیمی، دانشکده فنی، دانشگاه تهران، صندوق پستی: 4536-11365، تهران ـ ایران
AUTHOR
1. ASME MFC-3M, “Measurement of fluid flow in pipe using orifice, nozzle, and venturi,” American Society of Mechanical Engineers Standard )1989(.
1
2. R.C. Baker, “Low measurement handbook,” Cambridge University Pres, London )1987(.
2
3. J.M. Lafferty, “Foundations of vacuum science and technology,” New York, Wiley, 141-173 (1998).
3
4. B.G. Liptak, “Flow measurement handbook,” (1982-1993).
4
5. J.F. O'Hanlon, “A user's guide to vacuum technology,” 3rd (2003).
5
6. R.W. Miller, “Flow measurement engineering handbook,” Secend ed, Mc-Graw-Hill, New Yourk, Vol. 11, 27-40 (1989)
6
7. W. Jitschin, M. Ronzheimer, S. Khodabakhshi, “Gas flow measurement by means of orifices and venturi tubes,” Vacuum, Vol. 53, 181-185, (1999).
7
8. W. Jitschin, “Gas flow measurement by the thin orifice and the classical venturi tube,” Vacuum, Vol. 76, 89-100 (2004).
8
9. D.J. Tritton, “Physical fluid dynamics,” UK, Oxford University Press (1988).
9
ORIGINAL_ARTICLE
Calculation and Determination of Natural Frequencies for Fresh Fuel Transportation Package Set with ANSYS®10.0 Software
The fresh fuel for BNPP-1 is due to be transported inside special containers which are supposed to be designed to stand against vibrations and impacts in order to protect the fuel from any possible damage. In order to perform the structural dynamic analysis of the containers, while being subjected to impact of dynamic forces, it is necessary to perform the vibration analysis which will lead to the vibrational modes and their natural frequencies for the structure of the containers. The vibration opposition of the containers must be far beyond the critical resonance. The resonance frequencies about the natural frequency of the structure will cause the enhancement of the oscillation range and may be ended with its disintegration. Determination of the natural frequencies and their mode shapes can be achieved by vibration-analyzing-methods. The amount of the natural frequency of any structure depends strongly on its shape, material and its lean points, as well as the amount and the type of the loads which the structure will be subjected to. In the presente research, the container of the fresh fuel of BNPP-1 is simulated by ANSYS®10.0 and their ten natural frequency modes have been calculated.
https://jonsat.nstri.ir/article_525_b11ed8e94a6eb4befb682ab32d3918e9.pdf
2009-02-19
59
64
Natural Frequency
Critical Resonance
Vibration Modes
Transportation Package Set
Fresh Fuel
VVER-1000 Reactor
Y
Sedigh
1
مدیریت سوخت، شرکت تولید و توسعه انرژی اتمی ایران، سازمان انرژی اتمی ایران، صندوق پستی: 7484-19395، تهران ـ ایران
LEAD_AUTHOR
S.A
Azimfar
2
مدیریت سوخت، شرکت تولید و توسعه انرژی اتمی ایران، سازمان انرژی اتمی ایران، صندوق پستی: 7484-19395، تهران ـ ایران
AUTHOR
1. “Radioactive material transport Regulations,” Requirements #ST-1, IAEA, Vienna (1996).
1
2. “Radioactive material transport Regulations,” corrected in 1990, IAEA, Vienna (1985).
2
3. User Manual of ANSYS®10.0 Software (2007).
3
4. “Calculations proving the safety provided by TK-C5-B package set used to Transport VVER-1000 Fuel Assemblies,” JSC. TVEL (2002).
4
5. “Rules for climbing crane arrangement and safe operation,” 10-382-00 (1985).
5
6. “General regulations on safety and Physical Protection,” When Transporting Nuclear Materials (OPBZ-83)(1984).
6
ORIGINAL_ARTICLE
Investigation of Yield and Earliness Traits in Safflower Mutants in Irrigated and Drought Stress Condition
The safflower or Carthamus tinctorius belongs to Asteraceae family. As a forage and oil crop, it is commonly used in dry or non dry farms. In this research, the seeds of Zarghan 279 as a winter variety was radiated by Gamma ray in 80, 100, 150 and 200 Grey doses and they were sown in farm. The mutants after the second generation, were under dry stress and non stress conditions and they were grown and selected up to the 5 th generation, M5. Their traits were measured in the final generation of mutants. The results shows that in two conditions yield, days to buding, days to start of flowering, days to 50% flowering, days to maturity and difference of days to maturity and days to buding were significant between mutants at 1% level. The difference in the oil percentage in two conditions were not significant.
https://jonsat.nstri.ir/article_526_29e4e4f56534d5ac5a6967d8cb3b1392.pdf
2009-02-19
65
69
Safflower
Mutation
Earliness
Radiation Induced Mutants
K
Mozaffari
kamimof@yahoo.com
1
پژوهشکده تحقیقات کشاورزی، پزشکی و صنعتی، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 498-31485، کرج-ایران
LEAD_AUTHOR
A.A
Asadi
2
پژوهشکده تحقیقات کشاورزی، پزشکی و صنعتی، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 498-31485، کرج-ایران
AUTHOR
M
Rahimi
3
پژوهشکده تحقیقات کشاورزی، پزشکی و صنعتی، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 498-31485، کرج-ایران
AUTHOR
1. A.A. Jaradat and M. Shahid, “Patterns of phenotypic variation in a of Carthamus tinctorius L. from the middle east,” Genetic Resourcess and Crop Evalution, 53:2.225-244 (2006).
1
2. H. Ben Sala, H. Ibtissem, M. Brahim, “Comparison of yield components and oil content of selected safflower (Carthamus tinctorius L.) accessions in Tunisia,” Fifth International Safflower Conference. Williston North Dakota and Sidney, Montana, USA (2001).
2
3. ع.ر. نژادشاملو، ع.م. رضائی، م. کریمی، ”فنولوژی، شاخصهای رشد و اجزاء عملکرد ارقام گلرنگ بهاره در اصفهان،“ چکیده مقالات چهارمین کنگره زراعت و اصلاح نباتات ایران، صفحات 168-167 (1374).
3
4. ع.م. نادری درباغشاهی، ”بررسی تأثیر تنش خشکی بر خصوصیات کیفی و جوانهزنی بذور سه لاین گلرنگ در کشت تابستانه اصفهان،“ پایاننامه کارشناسی ارشد دانشگاه اصفهان (1382).
4
5. E. Esendal, “Safflower production and research in Turkey,” Fifth International Safflower Conference. Williston north Dakota and Sidney, Montana, USA (2001).
5
6. A.H. Omidi Tabrizi, “Correlation between traits and path analysis for grain and oil yield in spring safflower,” Sesame and Safflower Newsletter, 15 (2000).
6
7. E.B. Pasban, “Evalutinon of yield and components in New spiny genotype of safflower,” The Joint Agriculture and Natural Resources Symposium, Tabriz- ganja (2004).
7
8. M.A. Khadeer and S.Y. Anwar, “Induced mutation in the improvement of safflower (Carthamus tinctorius L.) In:Plant Mutation Breeding for Crop Iimprovement,” Vol. 1, International Atomic Energy Agency, Vienna (1991).
8
9. ر. برادران، ”بررسی رابطه ژنتیکی عملکرد و اجزاء آن و مطالعه همبستگی صفات مهم زراعی در گلرنگ از طریق تجزیه علیت،“ پایاننامه کارشناسی ارشد دانشگاه تهران (1374).
9
10. S.A. Patil, R.L. Ravikumar, T.G. Prabhu, G. Parameshwarppa, “A radiation induced polygenic variation homozygous Genotypes of safflower,” Fifth International Safflower Conference. Williston North Dakota and Sidney, Montana, USA (2001).
10
ORIGINAL_ARTICLE
Biosorption of Strontium from Aqueous Solution by the New Strain of Bacillus sp. Strain GT-83
An attempt was made to isolate bacterial strains capable of removing strontium biologically. In this study ten different water samples collected from Neydasht spring in the north of Iran and then the bacterial species were isolated from the water samples. The initial screening of a total of 50 bacterial isolates resulted in selection of one strain. The isolated strain showed a maximum adsorption capacity with 55mg strontium/g dry wt. It was tentatively identified as Bacillus sp. according to the morphological and biochemical properties, and called strain GT-83. Our studies indicated that Bacillus sp. GT-83 is able to grow aerobically in the presence of 50mM SrCl2, but its growth was inhibited at high levels of strontium concentrations. The biosorption capacity of Bacillus sp. GT-83 depends strongly on the pH solution. Hence the maximum strontium sorption capacity of Bacillus sp. GT-83 was obtained at pH 10, independent of absence or presence of MgCl2 of different concentrations. Strontium-salt biosorption studies were also performed at this pH values. The equilibrium biosorption of strontium was elevated by increasing the strontium concentration, up to 250mg/l for Bacillus sp. GT-83. The maximum biosorption of strontium was obtained at temperatures in the range of 30-35˚C. The Bacillus sp. GT-83 biosorbed 97mg strontium/g dry wt at 100mg/l initial strontium concentration without MgCl2. When MgCl2 concentration increased to 15%(w/v), these values dropped to 23.6mg strontium/g dry wt at the same conditions. Uptake of strontium within 5 min of incubation was relatively rapid and the absorption continued slowly thereafter.
https://jonsat.nstri.ir/article_527_46d70577970b7eebe0de507ffbc923ce.pdf
2009-02-19
70
75
Bacillus sp. GT-83
Biosorption
Neydasht Spring
Radionuclide
Strontium
Wastewater
1. G.J. Kirk and S. Staunton, “On the predicting the fate of radioactive cesium in soil beneath grassland,” Journal of Soil Science, 40, 71-84 (1989).
1
2. B.L. Carson, H.V. Ellis, J.L. McCann, “Toxicology and biological monitoring of metals in humans,” Chelsea, MI: Lewis Publishers (1986).
2
3. S. Ghorbanzadeh Mashkani, P. Tajer Mohammad Ghazvini, H. Ghafourian, “Biofiltration of Cs and Sr ions from aqueous solutions by native and chemically treated Azolla filiculoides,” International Journal of Ecological Economics and Statistic. 13, 17-24 (2009).
3
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13. S. Ghorbanzadeh Mashkani, F. Malekzadeh, H. Ghafurian, M.R. Soudi, P. Tajer Mohammad Ghazvini, “Biosorption of tungsten from aqueous solutions by new strain of Bacillus sp. MGG-83 isolated from Anzali lagoon,” Journal of Nuclear Science and Technology, 37, 22-28 (2006).
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14. S. Ghorbanzadeh Mashkani, P. Tajer Mohammad Ghazvini, H. Ghafourian, M.A. Ahmadi, “Biosorption of rhenium by new strain of Bacillus sp. MGG-83,” Journal of Nuclear Science and Technology, 38, 31-35 (2007).
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P. Tajer Mohammad Ghazvini, S. Ghorbanzadeh Mashkani, “Phytoremediation of aqueous solutions polluted by Cr(VI) and Pb(II) by Azolla: A new bioseparation process for wastewater treatment,” 10th International Conference on Environmental Science and Technology, Cosisland, Greece, September 5th - 7th, A-410- A-416 (2007).
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