ORIGINAL_ARTICLE
Describing VVER-1000 reactors fuel rod performance in the normal
operation and high burn-up conditions
The main purpose of the work is to develop a valid physical model and an accurate numerical technique to describe the occurred phenomenon of the VVER-1000 fuel rod, during its lifetime, especially for high burn up conditions. There are many factors involved in the fuel rod performance, which each of them, intricately affect its behavior during normal operation. The accurate prediction of the fuel behavior is obligatory and will be utilizable for the fuel designers. In geneval, fuel rod behavior is affected by the various chemical, mechanical, and thermo neutronic phenomena. For a detailed assessment of the fuel behavior inside the reactor core, the mentioned factors and the dominant aspects must be modeled accurately. The physical models and correlations used in this paper, are chosen in such a way that all the simulation results be in a good agreement with the available post-irradiation examination data (PIE) and outputs of the FRAPCON-3.3 fuel rod performance code.
https://jonsat.nstri.ir/article_992_31924c5559a77ce678e8f65c9c10e2da.pdf
2019-08-23
1
13
10.24200/nst.2019.992
Fuel behavior
Physical model
Simulation
VVER-1000
Frapcon
S
Talebi
sa.talebi@aut.ac.ir
1
گروه انرژی، دانشکدهی مهندسی انرژی و فیزیک، دانشگاه صنعتی امیرکبیر، صندوق پستی: 4413-15875، تهران ـ ایران
LEAD_AUTHOR
IAEA, Analysis of differences in fuel safety criteria for WWER and western PWR nuclear power plants / TECDOC-1381, (2003).
1
G.A. Berna, G.A. Beyer, K.L. Davis, D.D. Lanning, FRAPCON-3: A computer code for the calculation of steady-state, thermal-mechanical behavior of oxide fuel rods for high burnup, (1997).
2
K. Lassmann, TRANSURANUS: a fuel rod analysis code ready for use, J. Nucl. Mater., 188, 295–302 (1992).
3
[4] U.Ê. Bibilashvily, À.V. Medvedev, S.Ì. Bogatyr, V.I. Kouznetsov, G.À. Khvostov, START-3 code gap conductance modelling, Therm. Perform. High Burn. LWR Fuel., 369 (1998).
4
K.A. Terrani, D. Wang, L.J. Ott, R.O. Montgomery, J. Nucl. Mater., 448, 512-519 (2014).
5
P.E. MacDonald, J.M. Broughton, Cracked pellet gap conductance model: comparison of frap-s calculations with measured fuel centerline temperatures, (1975).
6
N.E. Todreas, M.S. Kazimi, Nuclear systems I: Thermal Hydraulic Fundamentals, Taylor & Francis, (1990).
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8
K. Lassmann, F. Hohlefeld, Nucl. Eng. Des., 103, 215-221 (1987).
9
K.J. Geelhood, W.G. Luscher, FRAPCON-3.5: A Computer Code for the Calculation of Steady-State, Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup, (2014).
10
Russia Federal Agency on Nuclear Energy, Bushehr NPP Final Safety Analysis Report, Moscow, (2003).
11
K.J. Geelhood, W.G. Luscher, FRAPCON-4: A Computer Code for the Calculation of Steady-State, Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup, 1 (2015).
12
F.W. Dittus, L.M.K. Boelter, Heat transfer in automobile radiators of the tabular type, University of California, (1930).
13
K. Ohira, N. Itagaki, Thermal conductivity measurements of high burnup UO2 pellet and a benchmark calculation of fuel center temperature, in: Proc. Am. Nucl. Soc. Meet. Light Water React. Fuel Performance, Portland, Oregon, 541 (1997).
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S.P.S. Badwal, Materials for solid oxide fuel cells, (1997).
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F.B. Tas, S. Ergun, Energy Convers. Manag., 72, 88–93 (2013).
16
F. Kreith, R.M. Manglik, M.S. Bohn, Principles of Heat Transfer, (2011).
17
IAEA, Advanced Fuel Pellet Materials and Designs for Water Cooled Reactors/TECDOC-1416, Tech. Comm. Meet. Held Brussels., (2004) 329.
18
D.L. Hagrman, G.A. Reymann, MATPRO-VERSION 11: a handbook of materials properties for use in the analysis of light water reactor fuel rod behavior, (1979).
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L.E. Herranz, A. Tigeras, Prog. Nucl. Energy., 52, 435–441 (2010).
20
J.E. Garnier, S. Begej, A.O. Desjarlais, R.P. Tye, Ex-Reactor Determination of Thermal Gap Conductance between Uranium Dioxide:Zircaloy-4 Interfaces, in: D.C. Larsen (Ed.), Therm. Conduct. 16, Springer US, Boston, MA, 211–219 (1983).
21
P.E. Macdonald, R.H. Smith, Nucl. Eng. Des., 61, 163-177 (1980).
22
C.M. Allison, G.A. Berna, R. Chambers, E.W. Coryell, K.L. Davis, D.L. Hagrman, D.T. Hagrman, N.L. Hampton, J.K. Hohorst, R.E. Mason, M.L. McComas, SCDAP/RELAP5/MOD3. 1 code manual, VOLUME I: CODE STRUCTURE, SYSTEM MODELS, AND SOLUTION METHODS, DT Hagrman, NUREG/CR-6150, EGG-2720., 1 (1993) 4–234.
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K.E. Carlson, R.A. Riemke, S.Z. Rouhani, R.W. Shumway, W.L. Weaver, RELAP5/MOD3 Code Manual Volume I: Code Structure, System Models and Solution Methods, US NRC NUREG/CR-5535, Washingt. (DC, USA) June., (1990).
24
W.G. Luscher, K.J. Geelhood, Material Property Correlations: Comparisons between FRAPCON-4.0, FRAPTRAN 2.0, and MATPRO, (2015).
25
M.J.F. Notley, I.J. Hastings, Nucl. Eng. Des., 56, 163–175 (1980).
26
L.O. Jernkvist, A.R. Massih, Analysis of the effect of UO2 high burnup microstructure on fission gas release, Ski Rep., 2, 56 (2002).
27
ORIGINAL_ARTICLE
Study of the VVER1000 reactor core fuel assemblies reaction to mass flux
changes, caused by lose of coolant accident, by means of the sound effect
The article aims in the studying of thermal-hydraulic simulation of the VVER-1000 reactor core fuel assemblies’ reaction to the mass flux changes which are caused by the lose of coolant accident and its sudden pressure drop. The analysis of mentioned accident is performed in concise periods (mili second) by the use of the sound effect. Time-related thermal-hydraulic equations were analyzed by the method of a compressible fluid in a single heated channel and were evaluated by the results of the mentioned transient, in a PWR reactor. The mentioned transient was simulated in RELAP5 code and results were compared to the previous ones. Then, 28 reactor fuel assemblies were studied, considering the 1/6 symmetry of VVER-1000 reactor and unique features of every assembly. Mass flux drop was happened the end of the channel, after a few seconds. It was observed that mass flux is at dependent on the role of every assembly in the production of core heat power. The acoustic effect reveals some of the perturbations in mass flux changes, considering every fuel assembly features.
https://jonsat.nstri.ir/article_993_f067d0dd50c1fe4c52359f1916f100bb.pdf
2019-08-23
14
21
10.24200/nst.2019.993
fuel assembly
VVER-1000
mass flux
sound effect
S
Heidari
s_heidari_in@yahoo.com
1
گروه مهندسی هستهای، واحد علوم و تحقیقات، دانشگاه آزاد اسلامی، صندوق پستی: 775-14515، تهران ـ ایران
AUTHOR
M
Rahgoshay
m-rahgoshay@sbu.ac.ir
2
گروه مهندسی هستهای، واحد علوم و تحقیقات، دانشگاه آزاد اسلامی، صندوق پستی: 775-14515، تهران ـ ایران
LEAD_AUTHOR
N
Vosoughi
nvosoughi@sharif.edu
3
دانشکدهی مهندسی، دانشکدهی مهندسی انرژی، دانشگاه صنعتی شریف، صندوق پستی: 8639-11365، تهران ـ ایران
AUTHOR
M
Athari
4
گروه مهندسی هستهای، واحد علوم و تحقیقات، دانشگاه آزاد اسلامی، صندوق پستی: 775-14515، تهران ـ ایران
AUTHOR
P.K. Chan, IEEE Transaction on Computer Aided Design, 10, 8, 1078–1079 (1991).
1
C.K. Ooi, K.N. Seetharamu, Z.A.Z. Alauddin, G.A. Quadir, K.S. Sim, T.J. Goh, Fast transient solutions for heat transfer, 2003, in Proceedings of the Conference on Convergent Technologies for the Asia-Pacific Region (IEEE TENCON ’03), 1, 469–473 (2003).
2
P. Liu, H. Li, L. Jin, W. Wu, S.X.D. Tan, J. Yang, IEEE Transactions on Computer-Aided Design of Integrated Circuits and Systems, 25, 12, 2882–2892 (2006).
3
K.N. Proskuryakov, Recent Adv Petrochem Sci, Volume 2 Issue 1 (2017).
4
N.E. Todreas, M.S. Kazimi, Nuclear systems II: Elements of thermal hydraulic design (Vol. 2). Taylor & Francis (1990).
5
G. Forti, E. Vincenti, The codes costanza for the dynamics of liquid cooled nuclear reactor, joint nuclear research center Ispra stablishment-Italy, reactor physics department reactor teory and analysis (1967).
6
M. Hosseini, H. Khalafi, S. Khakshournia, Progress in Nuclear Energy, 85, 108-120 (2015).
7
J.C.M. Leung, K.A. Gallivan, R.E. Henry, Critical Heat Flux Predictions During Blow down Transient, Argonne National Laboratory, Argonne, IL60439, U.S.A (1981).
8
AEOI, Reactor Final Safety Analysis Report VVER-1000 Bushehr, Chapter 4, Atomic Energy Organization of Iran (2005).
9
W. Wagner, H.J. Kretzschmar, International Steam Tables, Second edition, Faculty of Mechanical Engineering Chair of Thermo-dynamics (2007).
10
RELAP5/SCDAP//MOD3.2 Code Manuals, A Computer Code for Best-Estimate Transient Simulation of Light Water Reactor Coolant Systems During Severe Accidents, Prepared for the U.S. 1997, Nuclear Regulatory Commission, Idaho National Engineering and Environmental Laboratory, NUREG/CR-6150.
11
ORIGINAL_ARTICLE
Sample dose calculation for flexural strength test in Tehran research reactor reflector
Safety is one of the most critical issues in any test. The flexural test is a significant one to obtain material specifications. In this paper, a standard sample dose rate was calculated for the graphite flexural test in Tehran research reactor. Using different standards, the dose was computed at different distances and two periods of radiation, 15-40 days. Our calculations were performed with the ORIGEN and MCNPX codes. The impurity amounts of the material were measured by two methods of X-ray Fluorescence (XRF) and Inductively Coupled Plasma, Atomic Emission Spectroscopy (ICP-AES). The obtained results show that the Claiborne & Trubey standard is more stringent than other standards, and it has less than 2 μSv/h dose with the observance of 100cm distance and 20 days after irradiation. Moreover, calculations of the transfer chamber indicate that there is no limitation for the transport of the samples. Finally, it can be concluded that the considered method of this research can be used also for other materials at the reactor core.
https://jonsat.nstri.ir/article_995_45245fc775eedfcc719c07dde31c8259.pdf
2019-08-23
22
31
10.24200/nst.2019.995
Dose calculation
Flexural strength
Tehran reactor
ORIGEN
MCNPX
M.A
Amirkhani
1
پژوهشکدهی راکتور و ایمنی هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 1339-14155، تهران ـ ایران
AUTHOR
M
Hassanzadeh
mhasanzadeh@aeoi.org.ir
2
پژوهشکدهی راکتور و ایمنی هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 1339-14155، تهران ـ ایران
LEAD_AUTHOR
M
Asadi Asadabad
asadimohsen@gmail.com
3
پژوهشکدهی راکتور و ایمنی هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 1339-14155، تهران ـ ایران
AUTHOR
S.M
Mirvakili
4
پژوهشکدهی راکتور و ایمنی هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 1339-14155، تهران ـ ایران
AUTHOR
B.T. Kelly, Graphite—the most fascinating nuclear material. Carbon, 20, 1, 3-11 (1982).
1
H. Atsumi, T. Tanabe, T. Shikama, Journal of Nuclear Materials, 39, 581-584 (2009).
2
C. Hubert, K.O. Voss, M. Bender, K. Kupka, A. Romanenko, D. Severin, C. Trautmann, M. Tomut, Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 365, 509-514 (2015).
3
T.R. Allen, K. Sridharan, L. Tan, W.E. Windes, J.I. Cole, D.C. Crawford, G.S. Was, Nuclear Technology, 162, 3, 342-357 (2008).
4
R. Nightingale, Graphite in Nuclear Industry. New York and London Academic Press (1962).
5
P. Thrower, W. Reynolds, Journal of Nuclear Materials, 8, 2, 221-226 (1963).
6
C. Karthik, J. Kane, D.P. Butt, W.E. Windes, R. Ubic, Carbon, 86, 124-131 (2015).
7
ASTM, Standard Test Method for Flexural Strength of Manufactured Carbon and Graphite Articles Using Three-Point Loading at Room Temperature (2015).
8
Pelowitz, DB: MCNPX 2.6.0 manual, LANL, LA-CP-07-1473. Los Alamos National Laboratory (2008).
9
M. Bell, ORIGEN: the ORNL isotope generation and depletion code. Oak Ridge National Lab, Tenn. (USA) (1973).
10
V.P. Singh, M. Medhat, S. Shirmardi, Radiation Physics and Chemistry. 106, 255-260 (2015).
11
V. Lacoste, V. Gressier, H. Muller, L. Lebreton, Radiation protection dosimetry, 110, 135-139 (2004).
12
N.E. Holden, R.N. Reciniello, J.P. Hu, Health physics, 86, S110-S112 (2004).
13
J.P. Hu, N. Holden, R. Reciniello, in EPJ Web of Conference, EDP Sciences (2016).
14
H. Mayer, in The American Carbon Society’s 24th Biennial Conference on Carbon–CARBON (1999).
15
G.M. Farias, R.G. Wuilloud, S. Moyani, J.A. Gasquez, R.A. Olsina, L.D. Martinez, Journal of analytical toxicology, 26, 6, 360-364 (2002).
16
A. Puzas, V. Remeikis, Z, Ezerinskis, P. Serapinas, A. Plukis, G. Duskesas, Lithuanian Journal of Physics, 50, 4 (2010).
17
P. Brouwer, Theory of XRF. Almelo, Netherlands: PANalytical BV (2006).
18
I.O.F. Standardization, General requirements for the competence of testing and calibration laboratories: ISO/IEC (2005).
19
M. Batsala, B. Chandu, B. Sakala, S. Nama, S. Domatoti, Int J Res Pharm Chem, 2, 3, 671-680 (2012).
20
R. Plukienė, A. Plukis, A. Puzas, V. Remeikis, G. Duskesas, D. Germanas, Progress in Nuclear Science and Technology, 2, 421-426 (2011).
21
ASTM, D7301–11; Standard Specification for Nuclear Graphite Suitable for Components Subjected to Low Neutron Irradiation Dose. Annual Book of ASTM Standards, ASTM, West Conshohocken, PA (2011).
22
A. Standard, C 1233–09 Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials. Annual Book of ASTM Standards, ASTM, West Conshohocken, PA.
23
Institute N.S.T.R., TRR-FSAR-New Edition (2009).
24
H. Cember, Introduction to health physics. Introduction to health physics (1969).
25
ORIGINAL_ARTICLE
Design and simulation of the helicon plasma system with 1.5 kW RF
power and 13.56 MHz frequency
In this paper, a Helicon plasma system with Nagoya Type III antenna was designed and simulated by using COMSOL Multiphysics 5.2. In our simulation, all effective interactions and parameters in the plasma production process are considered. Besides, the cross-sections of the reactions which are occurred in the plasma with the energy range from 0.001 eV to 1MeV are applied in the software. Meanwhile, the Argon-Helicon plasma is produced by using Nagoya Type III antenna considering the following conditions: the magnetic field of 600 G, the antenna current 6 Ampere, with the operating gas pressure 10 mTorr and inlet gas flux of 50 (SCCM). Finally, the plasma density of the order 2×1018 m-3 and a temperature of 2.6 eV were obtained by using the Nagoya antenna. The effect of the variations of the current, which was applied to the Nagoya antenna, on the density and absorbed power of the Helicon plasma was also investigated. This simulation was made for seven operational helicon devices, and the results have seemed reasonable.
https://jonsat.nstri.ir/article_996_9567b1edaf2bfb002faf06d3b463ff22.pdf
2019-08-23
32
43
10.24200/nst.2019.996
Helicon plasma
RF plasmas
Simulation
S
Fazelpour
samanehfazelpour@ymail.com
1
پژوهشکدهی پلاسما و گداخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی، صندوق پستی: 51113-14399، تهران- ایران
AUTHOR
A
Chakhmachi
2
پژوهشکدهی پلاسما و گداخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی، صندوق پستی: 51113-14399، تهران- ایران
LEAD_AUTHOR
D
Iraji
d.iraji@gmail.com
3
دانشکدهی فیزیک و مهندسی انرژی، دانشگاه صنعتی امیر کبیر، صندوق پستی: 4413-15875، تهران- ایران
AUTHOR
M
Tafreshi
4
پژوهشکدهی پلاسما و گداخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی، صندوق پستی: 51113-14399، تهران- ایران
AUTHOR
H
Sadeghi
hosseinsadeghi.88@gmail.com
5
دانشکدهی فیزیک و مهندسی انرژی، دانشگاه صنعتی امیر کبیر، صندوق پستی: 4413-15875، تهران- ایران
AUTHOR
1. F.F. Chen, In Advanced Plasma Technology, ed. by R. d’Agostino, P. Favia, H. Ikegami, Y. Kawai, N. Sato and F. Arefi-Khonsari (Wiley-VCH, Berlin, 2006), Chap. 6.
1
2. Y.S. Hwang, I.S. Hong, G.S. Eom, Review of scientific instruments,69, 3, 1344-1348 (1998).
2
3. F.F. Chen, IEEE Transactions on plasma science, 36, 5, 2095-2110 (2008).
3
4. F.F. Chen, Plasma Physics and Controlled Fusion,33, 4, 339 (1991).
4
5. F.F. Chen, Physica Scripta 1990.T,30, 14 (1990).
5
6. F.F. Chen, Electrical Engineering Department, University of California, Los Angeles, CA 90095–1594, USA.
6
7. F.F. Chen, Plasma Sources Science and Technology, 21, 5, 055013 (2012).
7
8. O.V. Braginskii, A.N. Vasil’eva, A.S. Kovalev, Plasma Physics Reports, 27, 8, 699-707 (2001).
8
9. M. Light, F.F. Chen, Physics of Plasmas, 2, 4, 1084-1093 (1995).
9
10. A.R. Ellingboe, R.W. Boswell, Physics of Plasmas, 3, 7, 2797-2804 (1996).
10
11. F.F. Chen, R.W. Boswell, IEEE Transactions on Plasma Science, 25, 6, 1245-1257 (1997).
11
12. Y. Mouzouris, J.E. Scharer, Physics of Plasmas, 5, 12, 4253-4261 (1998).
12
13. F.F. Chen, University of Los Angeles Report LTP-806 June, (1998).
13
14. R.L. Stenzel, J.M. Urrutia, Physics of Plasmas, 23, 9, 092103 (2016).
14
15. A. Ganguli, R.D. Tarey, Indian Institute of Technology Delhi, New Delhi 110 016, India, CURRENT SCIENCE, 3, 10, 83 (2002).
15
16. D. Melazzi, V. Lancellotti, Plasma Sources Science and Technology, 24, 2, 025024 (2015).
16
17. I.V. Kamenski, G.G. Borg, Physics of Plasmas, 3, 12, 4396-4409 (1996).
17
18. F.F. Chen, Physics of Plasmas, 3, 5, 1783-1793 (1996).
18
19. T. Windisch, K. Rahbarnia, O. Grulke, T. Klinger, Plasma Sources Science and Technology, 19, 5, 055002 (2010).
19
20. C.A. Lee, G. Chen, A.V. Arefiev, R.D. Bengtson, B.N. Breizman, Physics of Plasmas,18, 013501 (2011).
20
21. G. Chen, A.V. Arefiev, R.D. Bengtson, B.N. Breizman, C.A. Lee, L.L. Raja, Physics of plasmas, 13, 123507 (2006).
21
22. A.W. Molvik, T.D. Rognlien, J.A. Byers, R.H. Cohen, A.R. Ellingboe, E.B. Hooper, H.S. McLean, B.W. Stallard, P.A. Vitello, Journal of Vacuum Science & Technology A: Vacuum, Surfaces, and Films, 14, 984 (1996).
22
23. X.M. Guo, J. Scharer, Y. Mouzouris, L. Louis, Physics of Plasmas, 6, 3400 (1999).
23
24. F.A.N.G. Tong-Zhen, W. Long, J. Di-Ming, Z. Hou-Xian, Chinese Physics Letters, 18, 1098 (2001).
24
ORIGINAL_ARTICLE
Single longitudinal mode operation of a 3 atm pulsed CO2 laser
with hybrid method
In this work, the hybrid configuration was used to produce the single longitudinal mode operation of pulsed CO2 laser with 14 cm long active volume at the pressure 3 atm. For this resean, a low pressure continuous wave CO2 laser with 120 cm long active volume is used. It was found that the emitted pulses of the system exhibit single mode behavior in above threshold condition and also at the pressures up to 7 mbar below threshold condition. To characterize the system performance, various parameters of the single mode pulses at different pressures and powers of the continuous wave laser were analyzed. Furthermore, the threshold pressure of the continuous wave laser for the single mode operation was obtained at about 9.5 mbar. It is shown that in both above and below threshold conditions, the single mode pulses have higher durations and rise times and also lower build- up times.
https://jonsat.nstri.ir/article_997_8d6b77b45c05362af97e5cef48373ce7.pdf
2019-08-23
44
50
10.24200/nst.2019.997
Single longitudinal Operation
Hybrid method
Pulsed CO2 Laser
S
Kazemi Sangsari
sajjadkazemi2284@gmail.com
1
پژوهشکدهی فوتونیک و فناوریهای کوانتومی، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 13-14399511، تهران ـ ایران
AUTHOR
S
Jelvani
sjelvani@aeoi.org.ir
2
پژوهشکدهی فوتونیک و فناوریهای کوانتومی، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 13-14399511، تهران ـ ایران
AUTHOR
M
Mollabashi
mollabashi@iust.ac.ir
3
پژوهشکدهی فوتونیک و فناوریهای کوانتومی، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 13-14399511، تهران ـ ایران
AUTHOR
M
Ilchi
m_ilchi@aut.ac.ir
4
پژوهشکدهی فوتونیک و فناوریهای کوانتومی، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 13-14399511، تهران ـ ایران
AUTHOR
Z
Pourhasannezhad
5
پژوهشکدهی فوتونیک و فناوریهای کوانتومی، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 13-14399511، تهران ـ ایران
AUTHOR
D
Ahadpour
dahadpour@aeoi.org.ir
6
پژوهشکدهی فوتونیک و فناوریهای کوانتومی، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 13-14399511، تهران ـ ایران
AUTHOR
K
Silakhori
ksilakhori@aeoi.org.ir
7
پژوهشکدهی فوتونیک و فناوریهای کوانتومی، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 13-14399511، تهران ـ ایران
LEAD_AUTHOR
O. Svelto, Principles of Lasers, 5th Ed., Springer-Verlag, (2010).
1
M. Endo, Gas Lasers, Taylor and Francis Group, USA, (2007).
2
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ORIGINAL_ARTICLE
Theoretical investigation of the behavior of spherical ion- acoustic
solitons in two-temperature plasma
The propagation of the small amplitude ion-acoustic solitary waves (IASWs) is studied in a plasma containing cold fluid ions and multi-temperature electrons (cool and hot electrons) with the nonextensive distribution. In this paper, we were firstly written a set of fluid equations in the spherical geometry. Then, spherical Korteweg–de Vries (KdV) equation was derived using a reductive perturbation method. The obtained spherical Korteweg–de Vries equation was solved using a homotopy perturbation method (HPM). Furthermore, the impact of the electron nonextensivity, the density ratio of electrons and ions and the temperature ratio on the characteristics of ion- acoustic solitary waves were studied. The analytical results show that a decrease in the electron nonextensivity increases the soliton ion- acoustic width. On the other word, it was observed that a reduction in the nonextensivity parameter increases the nonlinear coefficient of the KdV equation.
https://jonsat.nstri.ir/article_998_6442241438c8b5f20cd3774a46e91973.pdf
2019-08-23
51
59
10.24200/nst.2019.998
Soliton
Ion- acoustic waves
Multi-temperature plasma
KdV equation
HPM
M
Nezam
nazari123@yahoo.com
1
گروه فیزیک، دانشگاه شاهد، صندوق پستی: 159-18155، تهران ـ ایران
AUTHOR
A
Nazari Golshan
nazarigolshan@yahoo.com
2
گروه فیزیک، دانشگاه شاهد، صندوق پستی: 159-18155، تهران ـ ایران
LEAD_AUTHOR
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24
ORIGINAL_ARTICLE
Investigation of the coherent combination of a 19-fiber laser beam
characteristics to achieve a multi tens of kW at a distance of 10 km
In this paper, we used a coherent beam combination to design a 50 kW high power laser beam for energy applications. Because of the strong environmental turbulence, degrade the coherent beam combination advantages, low turbulence level is considered. Combining elements are composed of 19 polarized single mode 3 kW high power fiber lasers where are arranged in the co- two centric hexagonal rings. Each of the fiber a lasers has a collimator with a 30 mm beam spot size output. We extended the transmitting range to z=10 km and the improved filling factor up to f=0.91. Therefore, power loss at the side lobes are minimized and resulted in the rise of combination efficiency to 88%, which is the highest published result. The central spot size radius on the target is R=5.9 cm, where indicate 0.45 kW/cm2 power density. Also, the effect of Phase errors of the combining elements at the far- field, which cause the ray intensity scattering from the center spot to the side lobes is investigated.
https://jonsat.nstri.ir/article_999_4ae1bb641bdd1b57551092328e23a7a9.pdf
2019-08-23
60
71
10.24200/nst.2019.999
Fiber laser
Coherent combining
S.H
Ghasemi
1
دانشکدهی فنی، دانشگاه آزاد اسلامی واحد تهران جنوب، صندوق پستی: 4435-11365، تهران ـ ایران
LEAD_AUTHOR
A
Haghparast
2
باشگاه پژوهشگران جوان و نخبگان، واحد مرند، دانشگاه آزاد اسلامی، صندوق پستی: 161-54165، مرند ـ ایران
AUTHOR
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P. Sprangle, J. Penano, A. Ting, NAVAL RESEARCH LAB WASHINGTON DC (2006).
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Li. Yongzhong, Liejia Qian, Daquan Lu, Dianyuan Fan, Shuangchun Wen, Optical Fiber Technology, 15, 3, 226-232 (2009).
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Pu hou, Zejin Liu, Xiaojun Xu, Zilun Chen, Xiaolin Wang, Optics & Laser Technology, 41, 3, 268-271 (2009).
6
Phillip prangle, Bahman Hafizi, Antonio Ting, Richard Fischer, Applied Optics, 54, 31, F201-F209 (2015).
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8. M.A. Vorontsov, T. Weyrauch, Applied Optics, 55, 35, 9950-9953 (2016).
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J.R. Penano, P. Sprangle, B. Hafizi, Propagation of high energy laser beams through atmospheric stagnation zones, Naval research lab washington dc beam physics branch (2006).
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P. Sprangle, J. Penano, B. Hafizi, Propagation of high energy laser beams in various environments, Naval research lab washington dc (2007).
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Gregory D. Goodno , Charles P. Asman , Jesse Anderegg , Steve Brosnan, Steve Brosnan, Eric C. Cheung, Dennis Hammons, Hagop Injeyan, Hiroshi Komine, William H. Long, Michael McClellan, Stuart J. McNaught, Shawn Redmond, Randall Simpson, Jeff Sollee, Mark Weber, S. Benjamin Weiss, Michael Wickham, IEEE Journal of Selected Topics in Quantum Electronics, 13, 3, 460-472 (2007).
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30
ORIGINAL_ARTICLE
Studies on the adsorption behavior of uranium onto a synthesized hybrid
material based on the spherical SBA-15 and tin tungstomolybdophosphate
In the present work, a hybrid material, as an adsorbent based on a mesoporous silica nanoparticle Sainta Barbara Amorphous-15 (SBA-15) and inorganic adsorbent, tin tungsto-molybdo-phosphate (TWMP), was synthesized for the investigation of adsorption behavior of uranium in aqueous solution under ambient conditions. The synthesized hybrid was characterized by the X-ray diffraction, Fourier transfer infra-red, thermogravimetry, and N2 adsorption-desorption analysis. The obtained results confirm that TWMP has been immobilized on SBA-15 very well. Furthermore, the experimental results show that uranium adsorption on the hybrid is strongly influenced by the hydronium ion concentration, contact time, and initial concentration of uranium. The values of the calculated correlation coefficients of the linear regressions (R2) indicate that, the adsorption data are fitted by the Langmuir isotherm model very well. The obtained amount of RL (0.1) shows that the adsorption process is favorable. The amount of E obtained by the Dubinin-Radushkevich model, suggests that the predominant reaction mechanism is a physisorption process. Kinetic data of adsorption indicate that the adsorption process can be described by the pseudo second-order reaction rate model. Finally, the obtained maximum adsorption capacity of uranium (193.6 mg.g-1) on hybrid, indicates that the prepared material is a perfect candidate for the adsorption and removal of the uranium from wastewater.
https://jonsat.nstri.ir/article_1000_ef56915a80c2d384a26c81a70b9d38f6.pdf
2019-08-23
72
83
10.24200/nst.2019.1000
Uranium
Hybrid adsorbent
Spherical SBA-15
Tin Tungstomolybdophosphate
Adsorption
H
Aghayan
haghayan@aeoi.org.ir
1
پژوهشکدهی مواد و سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران ـ ایران
AUTHOR
R
Yavari
yavariramin@yahoo.com
2
پژوهشکدهی مواد و سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران ـ ایران
LEAD_AUTHOR
H
Ghasemi
hghasemi@aeoi.org.ir
3
پژوهشکدهی مواد و سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران ـ ایران
AUTHOR
T
Yousefi
taher_yosefy@yahoo.com
4
پژوهشکدهی مواد و سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران ـ ایران
AUTHOR
Z. Yi, J.S. Xu, M.S. Chen, W. Li, J. Yao, H.L. Chen, F. Wang, J. Radioanal. Nucl. Chem. 298, 955–961 (2013).
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K. Kiegiel, A. Abramowska, P. Biełuszka, G. Zakrzewska-Kołtuniewicz, S. Wołkowicz, J. Radioanal. Nucl. Chem., 311, 589–598 (2017).
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S.S. Kumar, P.S. Dhami, S.C. Tripathi, A. Dakshinamoorthy, Hydrometallurgy, 95, 170–174 (2009).
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53
ORIGINAL_ARTICLE
Synthesis of modified graphene/ZnO nanocomposite and its
application for removal of the heavy metal ions from aqueous solutions
The existence of heavy metals in nature is one of the pressing concerns because of their toxicity and threat to human life. The aim of this study is the preparation of suitable adsorbent for heavy metal adsorption from the waste water using nanotechnology. In this work, modified graphene/ZnO (MG/ZnO) nanocomposite was first synthesized. The as-prepared composite was then used as an adsorbent for heavy metal removal, and its adsorption efficiency was compared with the modified graphene and ZnO nanoparticles. Adsorption efficiency of the modified graphene/ZnO was found higher than modified graphene and ZnO nanoparticles. The influence of the effective parameters on the adsorption process was studied and optimized. The obtained optimum conditions were: time = 30 min, an adsorbent dosage of 0.03 g/L, pH of 6, and T = 25˚C. The experimental data were best described by the pseudo-second-order kinetic and Langmuir isotherm models. The obtained thermodynamic parameters indicate that the adsorption process was exothermic and spontaneous.
https://jonsat.nstri.ir/article_1001_f446e43b4b069b9f65dd32e6ca5413bd.pdf
2019-08-23
84
91
10.24200/nst.2019.1001
Nanocomposite
Modified graphene
ZnO
Heavy Metals
S.S
Sajadi
1
پژوهشکدهی مواد و سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران ـ ایران
LEAD_AUTHOR
S. Mehdizadeh, S. Sadjadi, S.J. Ahmadi, M. Outokesh, JEHSE. 12, 1-7 (2014).
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5
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8
V. Chandra, K.S. Kim, Chem. Commun., 13, 3942–3944 (2011).
9
V. Chandra, J. Park, Y. Chun, J.W. Lee, I. Hwang, K.S. Kim, ACS Nano., 7, 3979–3986 (2010).
10
L. Irannejad, S.J. Ahmadi, S. Sadjadi, M. Shamsipur, JICS. 15, 111–119 (2018).
11
X. Zhou, J. Zhang, H. Wu, H. Yang, J. Zhang, S. Guo, J. Phys. Chem. C., 115, 11957–11961 (2011).
12
M.J. Jaycock, G.D. Parfitt, Onichester Ellis Horwood Ltd, (1981).
13
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14
R. Kaur, J. Singh, R. Khare, S.S. Cameotra, A. Ali, Appl. Water. Sci., 3, 207–218 (2013).
15
I.S. Johari, N.A. Yusof, M.J. Haron, S.M.M. Nor, Polymer., 5, 1056-1067 (2013).
16
A. Örnek, M. Özacar, I.A. Şengil, Biochem. Eng.J., 37, 192-200 (2007).
17
ORIGINAL_ARTICLE
Stoichiometric relation for extraction of thorium from acidic nitrate
solutions with Cyanex272
The stoichiometric relation for the extraction of thorium(IV) from acidic nitrate solutions with Cyanex272 was investigated. The effects of the extractant and nitric acid concentrations were studied. The extracted species at three different acidities (low, middle, and high levels) were found to be [Th(NO3)(OH)3.HA], [Th(NO3)(OH)2A.HA], and [Th(NO3)4.HA], respectively, based on the slope analysis method. The results showed that the extraction of thorium follow solvation mechanism in low, 0.001 M and high, 8 M concentration Nitric acid medium. While, in the middle acid conditions, 1 M, is in the form of cation exchange. The extracted Th(IV) species contain one CYANEX 272 molecule in the all acidic ranges.
https://jonsat.nstri.ir/article_1002_170045981032321f89878b72ce0de81e.pdf
2019-08-23
92
99
10.24200/nst.2019.1002
Stoichiometric relation
Thorium extraction
Acidic nitrate solutions
Cyanex 272
S
Milani
salamdar@aeoi.org.ir
1
پژوهشکدهی مواد و سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران ـ ایران
LEAD_AUTHOR
M
Eskandari Nasab
meskandari@yahoo.com
2
بخش مهندسی معدن، دانشکدهی صنعت و معدن زرند، دانشگاه شهید باهنر کرمان، صندوق پستی: 7616914111، کرمان ـ ایران
AUTHOR
D.K. Hays, Mushakov, Andrey, www. Thoriumpower.com, 45 (2006).
1
J.E. Crawford, U.S Bur. Mines Bull, 556 (1956).
2
F. Habashi, Department of mining and metallurgy, Laval University, Quebec city, Canada, 430-440 (1993).
3
F.L. Cuthbert, National Lead Company of Ohio, United State of Amearica, 104-120 (1958).
4
B. Gupta, P. Malik, A. Deep, Department of chemistry, University of Roorkee, Roorkee, Journal of Radioanalytical and Nuclear Chemistry, 251, 451- 456 (2002).
5
N.E. El-Hefny, J.A. Daoud, Hot Laboratories Centre, Atomic Energy Authority, 13759, Cairo, Egypt, Journal of Radioanalytical and Nuclear Chemistry, 261, 357-363 (2004).
6
M. Karve, C. Gaur, Department of chemistry, University of Mumbai, Vidyanagari, Mumbai 400 098, India, Journal of radioanalytical and nuclear chemistry, 270, 461-464 (2006).
7
S.K. Sahu, M.L.P. Reddy, T.R. Ramamohan, Radiochimica Acta 88, 33-37 (2000).
8
S.I. El-Dessouky, N.E. El-Hefny, J.A. Daoud, Radiochim. Acta 92, 25–29 (2004).
9
S.A. Milani, M. Eskandari Nasab, J. of Nuclear Sci. and Tech., 63, 24-34 (2013).
10
C. Moulin, B. Amekraz, S. Hubert, V. Moulin, Analytica Chimica Acta, 441,269-279 (2001).
11
R.K. Biswas, H.P. Singha, Council of scientific & industrial research, New Delhi, Indian journal of chemical technology, (2007) 269-275.
12
E.K. Hyde, Lawrence radiation laboratory, University of California, Berkeley, California, 7-15 (1960).
13
J. Bjerrum, DISS, Copenhagen. (1941).
14
ORIGINAL_ARTICLE
Mineralization aspects of trace and rare earth elements in the brecciated rocks
in the Se-Chahun ore deposit: insights from mineralogical and geochemical evidence
Mineralogical examination of the gangue and ore parts of the Se-Chahun magnetite-apatite ore deposit revealed the existence of Th and REE bearing minerals with paragenetic relationships with amphiboles, magnetite and calcite. Trace and REE host minerals are found in both of the gangue and the magnetite-apatite ore showing remarkable concentration in a phase referred to as the brecciated phase. This zone (phase) is characterized by high amounts of trace (Th) and light rare earth elements including La, Ce, Pr and Nd that were revealed in geochemical analysis. Mineralization of these elements is related to fluids appeared after magnetite mineralization in the region and resulted in metasomatism of the host rocks and a part of the ore and also concentration of the REE and trace elements as phosphates and silicates, respectively. There is not a clear key concerning the origin of these fluids but based on the geochemical evidence, the probable provenance is thought to be related to the magmas derived from the arc related subvolcanic bodies injected in subduction zones. Based on the paragenetic and geochemical evidence, a part of these elements is transported by carbonate complexes and accumulated in the brecciated rocks.
https://jonsat.nstri.ir/article_1003_8e05396a3f5563e4c2e348b7313dea31.pdf
2019-08-23
100
107
10.24200/nst.2019.1003
Mineralogy
Trace and rare earth elements
Brecciated phase
Sechahun ore deposit
Gh
Mirzababaei
1
بخش زمینشناسی، دانشکده علوم زمین، دانشگاه شهید بهشتی، صندوق پستی: 69411-19839، تهران ـ ایران
LEAD_AUTHOR
M
Yazdi
m-yazdi@sbu.ac.ir
2
بخش زمینشناسی، دانشکده علوم زمین، دانشگاه شهید بهشتی، صندوق پستی: 69411-19839، تهران ـ ایران
AUTHOR
M.R
Rezvanianzadeh
mrezvanianzade@modares.ac.ir
3
پژوهشکدهی مواد و سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران ـ ایران
AUTHOR
M
Behzadi
m_behzadi@sbu.ac.ir
4
بخش زمینشناسی، دانشکده علوم زمین، دانشگاه شهید بهشتی، صندوق پستی: 69411-19839، تهران ـ ایران
AUTHOR
M
Ghannadi Maraghe
mghanadi@aeoi.org.ir
5
پژوهشکدهی مواد و سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران ـ ایران
AUTHOR
1. H. Becker, H. Forster, H. Softfl, Zeitschriffti ir Geophysikv, 39, 953-963 (1973).
1
2. Z. Bonyadi, G.J. Davidson, B. Mehrabi, S. Meffre, F. Ghazban, Chemical Geology,281, 253–269 (2011).
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3. H. Förster, A. Jafarzadeh, Economic Geology, 89, 1697-1721 (1994).
3
4. S. Mohseni, A. Aftabi, Investigation on the Rapitan banded iron formation and mineralization in central Iranian iron ore field: Unpublished M. Sc. thesis, Shahid Bahonar University of kerman, 284 (in Persian) (2007).
4
5. F. Moore, S. Modabberi, Journal of sciences,14, 259-270 (2003).
5
6. A. Rajabi, C. Canet, E. Rastad, P. Alfonso, Ore Geology Reviews, 64, 328-353 (2014).
6
7. K. Khoshnoodi, M. Behzadi, M. Gannadi-Maragheh, M. Yazdi, Geologia Croatica, 70, 53-69 (2017).
7
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8
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10 A. Haghipour, Geological Survey of Iran (1977).
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11 A. Haghipour, G. Pelissier, Geological Survey of Iran, 8, 10-68 (1977).
11
12. F.M. Torab, Geochemistry and Metallogeny of Magnetite- apatite Deposits of the Bafq Mining District, Central Iran: Ph.D Thesis, Clausthal University of Technology, Faculty of Energy and Economic Sciences, 131 (2008).
12
13. J. Ramezani, R. Tucker, American Journal of Science, 303, 622-665 (2003).
13
14. S.S. Sun, W.F. McDonough, Geological Society of London, 42, 313-345 (1989).
14
15. W.V. Boynton, Elsevier Sci. Publ. Co., Amsterdam, 63-114 (1984).
15
16. F. Pirajno, Hydrothermal processes and mineral systems, Springer, 1250 (2009).
16
17.J.A. Kinnaird, Journal of African Earth Science, 3, 229-252 (1985).
17
18. A. Kontonikas-Charos, C.L. Ciobanu, N.J. Cook, Journal of Lithos,208-209, 178-201 (2014).
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19
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21. S.F Foley, M.G. Barth., G.A. Jenner, Geochimica et Cosmochimica Acta, 64, 933–938 (2000).
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22. A. Schmidt, S. Weyer, T. John, G.P. Brey, Geochimica et Cosmochimica Acta, 73, 455–468 (2009).
22
23. S. Klemme, S. Prowatke, K. Hametner, D. Gunther, Geochimica et Cosmochimica Acta,69, 2361–2371 (2005).
23
ORIGINAL_ARTICLE
Preparation of tissue equivalent conductive polyamide/polyethylene
nanocomposite containing carbon nanotubes as electrode of the
gaseous microdosimeters
The aim of this study is preparing a conductive tissue equivalent composite similar to expensive and limited access commercial A-150 plastic, in which, the Conductive Carbon Nanotubes (CNT) are used instead of black carbon. For this rescan, to obtain more conductivity nanocomposites of polyamide/polyethylene (PA/PE) containing 1 to 4% carbon nanotube were made by melt mixing. The resulting electrical conductivity of the composite with 3% CNT reached to 3× 10-6 S/cm which is in the range of semi-conductive materials. The Scanning Electron Microscopy (SEM) and Transmission Electron Microscopy (TEM) pictures show an electrical network formation in continuous PA phase and at the interface of two phases. In the studies of mechanical properties, a significant increase in the modulus of PA/PE/CNT nanocomposite with 3% CNT was observed. Meanwhile, determination of the density and percentage of the elements of this nanocomposite indicated that the obtained amounts were similar to that declared for the muscle tissue and A-150 plastic. Farther, Microdosimetry calculations showed that the linear energy distributions obtained from the microdosimeters with a wall of PA/PE/CNT nanocomposite and A-150, are well compatible. Therefore, this composite could be a suitable substitute for A-150, as an electrode of the gaseous microdosimeters
https://jonsat.nstri.ir/article_1004_978dbfe44b6fc233e92e0c3e1fe40913.pdf
2019-08-23
108
116
10.24200/nst.2019.1004
Nanocomposite
Polyamide/polyethylene
Tissue equivalent
A-150 plastic
Microdosimetry
F
Khoylou
fkhoylou@aeoi.org.ir
1
پژوهشکدهی کاربرد پرتوها، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 3486-11365، تهران ـ ایران
LEAD_AUTHOR
A
Akhavan
azakhavan@aeoi.org.ir
2
پژوهشکدهی کاربرد پرتوها، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 3486-11365، تهران ـ ایران
AUTHOR
F
Naimian
fnaimian@aeoi.org.ir
3
پژوهشکدهی کاربرد پرتوها، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 3486-11365، تهران ـ ایران
AUTHOR
A
Moslehi
moslehi.amir@yahoo.com
4
پژوهشکدهی کاربرد پرتوها، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 3486-11365، تهران ـ ایران
AUTHOR
H.H. Rossi, M. Zaider, Microdosimetry and its applications, Springer-verlag (1996).
1
ICRU Report 36, Microdosimetry, International Commission on Radiation Units, (1983).
2
A. Moslehi, G. Raisali, M. Lamehi, Radiat. Prot. Dosim., 173, 286-292 (2017).
3
L.A. Braby, G.W. Johnson, J. Barthe, Radiat. Prot. Dosim., 61, 351-379 (1995).
4
F.R. Shonka, R.J. Ernest, F. Gioacchino, Method of using and manufacturing plastic equivalent to organic materials, US 3005794 (1961).
5
J. Barthe, J.M. Bordy, Biological tissue-equivalent polymer composition having a very high resistivity, US 5569699A (1996).
6
H. Pang, L. Xu, D. Yan, Z. Li, Prog. Poly. Sci., 39, 1908-1933 (2014).
7
W. Zhang, A.A. Dehghani-Sanj, J. Mater. Sci., 42, 3408-3418 (2007).
8
F. Xiang, Y. Shi, X. Li, T. Huang, C. Chen, Y. Peng, Y. Wang, Eur. Polym. J., 48, 350-361 (2012).
9
F. Tanasa, M. Zanoaga, Y. Mamunya, Int. Conf. Scientific Papers, (2015).
10
L. Li, W-H Ruan, M-Q Zhang, M-Z Rong, Polym. Letters, 9, 77-83 (2015).
11
H. Pang, D. Yan, Y. Bao, J.B. Chen, C. Chen, Z. Li, J. Mater. Chem., 22, 23568-23575 (2012).
12
S. Malekie, F. Ziaie, Nucl. Instrum. Methods Phys. Res. A: Accelerators, Spectrometers, Detectors and Associated Equipment, 791, 1-5 (2015).
13
N. Grossiord, J. Loos, L.V. Laake, M. Maugey, C. Zakri, C.E. Koning, A.J. Hart, Advanced Functional Materials, 18, 3226-3234 (2008).
14
P. Potschke, A.R. Bhattacharyya, A. Janke, Polymer, 44, 8061-8069 (2003).
15
L.J. Goodman, Phys. Med. Biol., 23, 753-758 (1978).
16
C. Constantinou, Tissue substitutes for particulate radiations and their use in radiation dosimetry and radiotherapy, PHD Thesis, 47 (1978).
17
M. Damijan, A. Natas, E. Pavs, F.X. Hart, Electric properties of tissues, www.lifvation. com.
18
S. Malekie, F. Ziaie, Nucl. Instrum. Methods, Phys. Res. A: Accelerators, Spectrometers, Detectors and Associated Equipment, 816, 101-105 (2016).
19
L. Wang, J. Hong, G. Chen, Polym. Eng. Sci., 50, 2176-2181 (2010).
20
L.J. Goodman, Phys. Med. Biol., 23, 753-758 (1978).
21
Y. Mamunya, V. Levchenko, G. Boiteux, G. Seytre, M. Zanoaga, F. Tanasa, E. Lebedev, Polym. Composites, DOI 10.1002/pc.23434, (2015).
22
P.J. Brigandy, Electrically conductive multiphase polymer blend carbon based composites, Lehigh University, Theses and Dissertations, 26-27 (2014).
23
ICRU Report 44, Tissue substitutes in radiation dosimetry and measurements, International Commission on Radiation Units (1984).
24
ORIGINAL_ARTICLE
Solvent extraction of uranium (VI) from leach liquor solution of Bandar Abbas Gachin ore using Alamine 336
Uranium (VI) solvent extraction from the acidic sulfate solutions by Alamine 336 diluted in kerosene has been investigated. The effect of the contact time between phases, sulfuric acid concentration, extractant concentration, uranium concentration, organic/aqueous phase ratio, and temperature were studied. The results demonstrated that the uranium extraction was a fast, exothermic, and spontaneous reaction. Log Kex is calculated to be 5.94. The process parametric variation studies indicated a strong influence of sulfuric acid concentration on the extraction percentage of uranium. The extraction percentage was increased with an increase in the extractant concentration as well as the organic/aqueous phase ratio and decreased with an increase in the uranium concentration. Using 0.05 mol L-1 Alamine 336˚C at 25˚C with organic/aqueous phase ratio of 1:1, an extraction percentage of about 99.72% was achieved when the H2SO4 concentration was 0.15 mol L-1. The uranium extraction from the leach liquor solution was done under these optimum conditions, and iron (ІІІ) removal has investigated. Uranium stripping from the loaded solvent was carried out by many salt and acid solutions in the four steps. The effect of temperature was studied, and for the first time in this study, the enthalpy change of stripping reaction by using various chemical agents was obtained. 99.87% of uranium loaded in the organic phase was removed by 0.5 mol L-1 (NH4)2CO3 in a single stripping step.
https://jonsat.nstri.ir/article_1005_7eb30e0cdb7c4dc2c7e7fc2df4285bea.pdf
2019-08-23
117
127
10.24200/nst.2019.1005
Solvent extraction
Back- Extraction
Uranium
Leach Liquor
Alamine 336
F
Zahakifar
fzahakifar@aeoi.org.ir
1
پژوهشکدهی مواد و سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران ـ ایران
AUTHOR
R
Davarkhah
rdavarkhah@yahoo.com
2
پژوهشکدهی مواد و سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران ـ ایران
AUTHOR
A
Charkhi
acharkhi@aeoi.org.ir
3
پژوهشکدهی مواد و سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران ـ ایران
LEAD_AUTHOR
M
Torab Motaedi
mmostaedii@aeoi.org.ir
4
پژوهشکدهی مواد و سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران ـ ایران
AUTHOR
1. M.E. Nasab, Fuel, 116, 595-600 (2014).
1
2. A. Gharib, Uranium refining technology in Iran, AEOI, (2001).
2
3. V. Opratko, Purification of yellow cake, U.S. Patent, 3, 174, 821 (1965).
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4. J.R. Kumar, J.S. Kim, J.Y. Lee, H.S. Yoon, Sep. Pur. Rev, 40, 77-125 (2011).
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6. F. Moore, Long-Chain Amines, Anal. Chem, 29, 1660-1662 (1957).
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9. J.R. Kumar, J.S. Kim, J.Y. Lee, H.S. Yoon, J. rad. Nucl. chem,285, 301-308 (2010).
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10. K. Nazari, R. Mahmoudi, J. Nucl. Sci. Tech, 36, 19-26 (2006).
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11. C. Yu, S. Guoxin, Z. Zhenwei, H. Yufen, S. Sixiu, J. Rad. .Nucl. Chem, 272, 199-201 (2007).
11
12. J.L. Lapka, A. Paulenova, M.Y. Alyapyshev, V.A. Babain, R.S. Herbst, J.D. Law, Rad. Acta Inter. J. Chem. Asp. Nucl. Sci. Tech, 97, 291-296 (2009).
12
13. J.S. Kim, H.S. Han, S.J. Kim, S.D. Kim, J.Y. Lee, C. Han, J.R. Kumar, J. Radi. and Nucl. Chem., 307, 843-854 (2016).
13
14. C.J. Kim, J.R. Kumar, J.S. Kim, J.Y. Lee, H.S. Yoon, J. Braz. Chem. Soc, 23, 1254-1264 (2012).
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15. C. Morais, L.A. Gomiero, W.S. Filho, H. Rangel, Min. engin., 18, 1331-1333 (2005).
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16. J. Rydberg, revised and expanded. (2004): CRC Press.
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17. F. Hurst, D. Crouse, Oak Ridge National Lab., Tenn, (1961).
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18. V. Pandey, A. Chakraborty, N. Maity, Preparation of nuclear grade uranium oxide from Jaduguda leach liquor, (1991).
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19. D.J. Crouse, K. Brown, Amine extraction processes for uranium recovery from sulfate liquors., Oak Ridge National Laboratory, 1 (1956).
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20. D.J. Crouse, K. Brown, Oak Ridge National Lab., Tenn, Vol. I, (1955).
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21. G. Ramadevi, T. Sreenivas, A.S. Navale, N.P.H. Padmanabhan, J. Rad. Nucl. Chem,294,13-18 (2012).
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