ORIGINAL_ARTICLE
Magnetic Pulse Compression in Power Supplies of Radiation Generator Devices
High power pulses with low widths have many applications in radiation generator devices as flash radiography and high power microwave generators. One of the compression methods of high power pulses is magnetic pulse compression. In this paper a Tesla generator with saturated core which produces a 200kV voltage pulse has been designed and then the effect of saturation of the core in the compression of the output pulse using Proteus and CST EM Studio codes was studied. Our studies showed that with saturation of the transformer’s core, the magnetic permeability and hence the inductance of the transformer’s coils will decrease and consequently the frequency of current oscillations in the transformer will momentarily increase where it will result in the decrease of the output pulse width.
https://jonsat.nstri.ir/article_414_22c93e04dc82aef4fab1de4064ee4f47.pdf
2011-08-23
1
7
Magnetic Pulse Compression
Tesla Generator
High Power Pulse
Pulsed Power Supply
A
Sadeghipanah
1
گروه کاربرد پرتوها، دانشکده مهندسی هستهای، دانشگاه شهید بهشتی، صندوق پستی: 1983963113، تهران- ایران
AUTHOR
F
Abbasi Davani
fabbasi@sbu.ac.ir
2
گروه کاربرد پرتوها، دانشکده مهندسی هستهای، دانشگاه شهید بهشتی، صندوق پستی: 1983963113، تهران- ایران
LEAD_AUTHOR
Marco Denicolai, Tesla Transformer for experimentation and research–Helsinki university of technology–Licentiate thesis, 2-10, 24-28, 30 (May 2001).
1
Gennady A. Mesyats, Pulsed Power–Springer Science+Business Media, Inc., 251-256 (USA 2005).
2
A.I. Ryabchikov, et al, “Upgrading of the high-current accelerator "TONUS″,” Nuclear Physics Institute at Tomsk Polytechnic University, Plenum Publishing Corporation, Tomsk (Russia 1977).
3
ORIGINAL_ARTICLE
The Estimation of Gamma Dose in a Mixed Neutron-Gamma Radiation Field Using LiF:Mg,Ti (TLD-600) Thermoluminescence Dosimeter
In this work the ratio of the 4th peak to the 5th peak of a LiF:Mg,Ti (TLD-600) thermoluminescence dosimeter has been used to estimate the gamma dose in a mixed neutron-gamma radiation field. The samples were first exposed to the known neutron and gamma doses from Am-Be and 137Cs sources. Then, the contribution of the gamma dose in the mixed field was changed from 20% to 52% of the total dose. For this purpose by employing a computer program based on Levenberg-Marquart algorithm, and by using thermoluminescence general order model for the glow profile deconvolution, the ratio of the 4th to 5th peaks was determined. Finally, the peak ratios have been related to the contribution of the gamma dose in the mixed neutron gamma radiation field.
https://jonsat.nstri.ir/article_415_2e0257d297c2f7f86fab68486225a972.pdf
2011-08-23
8
14
Thermoluminesacence
Neutron Dosimetry
Mixed Neutron-Gamma Field
Two Peak Method
M
Zahedifar
1
گروه فیزیک، دانشگاه کاشان، صندوق پستی: 51167-87317، کاشان ـ ایران
LEAD_AUTHOR
M
Jafarizadeh
2
امور حفاظت در برابر اشعه، سازمان انرژی اتمی ایران، صندوق پستی: 1339-14155، تهران ـ ایران
AUTHOR
E
Sadeghi
sdgh@kashanu.ac.ir
3
گروه فیزیک، دانشگاه کاشان، صندوق پستی: 51167-87317، کاشان ـ ایران
AUTHOR
H
Shakhusi
4
گروه فیزیک، دانشگاه کاشان، صندوق پستی: 51167-87317، کاشان ـ ایران
AUTHOR
V. Chernov, B. Rogalev, A. Nepomnyaschikh, V. Cherepanov, “Error analysis of neutron dose measurment in mixed gamma-neutron fields by a two peak TL method,” Radiat. Prot. Dosim. 49, 443-449 (1993).
1
E.X. Rank and R.B. Theus, “Neutron dosimetry with CaF2:Tm,” IEEE Trans. Nucl. Sci., NS-26(1), 1590-1592 (1979).
2
J.B. Dielhof, A.J.J. Bos, J. Zoetelief, J.J Broerse, “Sensitivity of CaF2 thermoluminescent materials to fast neutrons,” Radiat. Prot. Dosim. 23, 405-408 (1998).
3
W. Hoffman, and B. Prediger, “Heavy particle dosimetry with high temperature peaks of CaF2:Tm and 7Lif phosphors,” Radiat. Prot. Dosim. 6, 149-152 (1983).
4
P. Meissner, U. Beink, J. Rassow, “Applicability Of TLD-700 detectors for dosimetry in d(14)+Be neutrons fields,” Radiat. Prot. Dosim. 23, 421-424 (1988).
5
B.B. Schachar and Y.S. Horowitz, “Dosimetric characterisation of the high temperature peaks of LiF:Mg, Ti and CaF2:Tm using computerised glow curve deconvolution,” Radiat. Prot. Dosim. 22, 87-96 (1988).
6
A.S. Pradhan, J. Rassow, P. Meissner, “Fast neutron response of CaF2: Tm teflon TLD discs of different thickness,” Radiat. Prot. Dosim. 15, 233-266 (1986).
7
Y.S. Horowitz, and B. Ben Schachar, “Sensitised TLD-700 for neutron-gamma dosimetry at radiation dose levels,” Radiat. prot. Dosim. 33, 263-266 (1990).
8
Y.S. Horowitz and D. Yossian, “Computerised glow curve doconvolution: application to thermoluminescence dosimetry,” In: Proc Int. Congr. on Radiation Protection, Vienna. Vol. 4, 293-295 (1996).
9
T.M. Piters, A.J.J. Bos, J. Zoetelief, “Thermoluminescence dosimetry in mixed neutron-gamma radiation fields using glow curve superposition,” Radiat. Prot. Dosim. 44, 305-308 (1992).
10
N. Horiuchu, T. Sato, H. Morimoto, “Simultaneous evaluation of the neutron and gamma dose with a single 6LiF TLD,” Nucl. Instrum. Methods A 317, 545-552 (1992).
11
D. Youssian and Y.S. Horwitz, “Estimation of gamma dose in neutron dosimetry using peak 4 to peak 5 ratios in LiF:Mg,Ti (TLD-100/600),” Radiat. Prot. Dosim. 77, 151-158 (1998).
12
A. Delgado, J.L. Muniz, J.M. Gomez Ros, A.M. Romero, R. Rodrıguez, “On the use of LiF TLD-600 in neutron-gamma mixed fields,” Radiat. Prot. Dosim. 125, 1-4, 327–330 (2007).
13
A. Triolo, M. Marrale, M. Brai, “Neutron-gamma mixed field measurements by means of MCP-TLD-600 dosimeter pair,” Nucl. Instrum. methods B 264, Issue 1, 183-188 (2007).
14
G. Kitis, J.M. Gomez Ros, J.W.N. Tuyn, “Thermoluminescence glow-curve deconvolution functions for first, second and general order of kinetics,” J. Phys. D:Appl. Phys. 31. 2636–2641 (1998).
15
ORIGINAL_ARTICLE
Use of Hydroxyapatite Prepared by Sol-Gel Method for Gamma Ray and Electron Beam Dosimetry
In this research, radiation dosimetry was made through measuring free radicals induced in synthetic hydroxyapatite (HAP) using EPR spectroscopy. At the first step, the hydroxyapatite nano-powders were synthesized via sol-gel method. The produced powders were passed through a thermal treatment, weighted and packed. Then, the samples were irradiated at different dose rates using 60Co γ-ray and 10MeV electron beam radiation at a high dose range. The EPR signal intensity of hydroxyapatite samples were measured at room temperature in the air. Subsequently, the variations of the EPR signal intensities were constructed as peak-to-peak signal amplitude and were compared with alanine and bone powder samples. The results showed that the EPR signal intensity of the HAP samples are several times higher than alanine and bone powder and are saturated at the higher dose rates in comparison with other species.
https://jonsat.nstri.ir/article_416_f624c08fa7ef72bbfece00c06b35d92a.pdf
2011-08-23
15
21
EPR Spectroscopy
Hydroxyapatite
Sol-Gel Method
Dosimetry
Gamma Ray and Electron Beam
N
Hajiloo
nhajiloo676@gmail.com
1
پژوهشکده تحقیقات کشاورزی، پزشکی و صنعتی، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 498-31485، کرج ـ ایران
AUTHOR
F
Ziaie
fziaie@aeoi.org.ir
2
پژوهشکده تحقیقات کشاورزی، پزشکی و صنعتی، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 498-31485، کرج ـ ایران
LEAD_AUTHOR
M
Hesami
3
پژوهشکده کاربرد پرتوها، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 389-89175، یزد ـ ایران
AUTHOR
1. W. Stachowics, K. Ostrowski, A. Dziedzic-Goclawski, A. Komender, “Sterilization and preservation of biological tissues by ionizing radiation,” Panel Proc. Series IAEA, Vienna, STVPUB/247, 15 (1970).
1
2. K. Mahesh, D.R. Vij(eds) “Techniques of radiation dosimeter,” Wily Eastern Ltd., New Delhi, India (1985).
2
3. K.W. Bögl, D.F. Regulla, M.J. Suess, “Health impact, identification, and dosimetry of irradiated food,” Report of a WHO Working Group. Berich des Institute für Strahlenhygiene des Bundesgesundheitsarntes Neuherberg, FRG, ISH‑125 (1988).
3
4. F. Ziaie, W. Stachowicz, G. Strzelczak, S. Al-Osaimi, “Using bone powder for dosimetric system EPR response under the action of gamma irradiation,” Nukleonika, 4, 603-608 (1999).
4
5. P. Moens, P. De Volder, R. Hoogewijs, F. Callens, R. Verbeeck, “Maximum-likelihood common factor analysis as a powerful tool in decomposing multycomponent EPR powder spectra,” J. Magn. Reson., 101, 1-15 (1993).
5
6. H.P. Schwarcz, “ESR study of tooth enamel,” Nucl, Tracks, 10, 865-867 (1985).
6
7. J. Talpe, “Theory of experiments in paramagnetic resonance,” Pergamon Press, New York, First Edition (1971).
7
8. M.F. Desrosiers, A.A. Romanyukha, “Medical and workplace application,” The National Academic Press (1998).
8
9. IAEA, “Use of electron paramagnetic resonance dosimetry with tooth enamel for retrospective dose assessment,” TECDOC-1331 (2002).
9
F. Ziaie, N. Hajiloo, H. Fathollahi, S.I. Mehtieva, “Bone powder as EPR dosimetry system for electron and gamma radiation,” NUKLEONIKA, 54(4) 267−270 (2009).
10
M.H. Fathi, A. Hanifi, “Evaluation and characterization of nanostructure hydroxyapatite powder prepared by simple sol–gel method,” Materials Letters 61, 3978–3983 (2007).
11
S. Kim and P.N. Kumta, “Sol-gel synthesis and characterization of nanostructured hydroxyl-apatite powder,” Materials Science and Engineering, B111, 232-236 (2004).
12
JCPDS Card, 9-432 (1994).
13
S. Kweh, K. Khor, P. Cheang, “An in vitro investigation of plasma sprayed hydroxyapatite(HA) coatings produced with flame-spheroidized feedstock,” Biomaterials; 23, 775–785 (2002).
14
K. Ishikawa, S. Takagi, L. Chow, K. Suzuki, “Reaction of calcium phosphate cements with different amounts of tetracalcium phosphate and dicalcium phosphate anhydrous,” J. Biomed Mater Res A; 46, 405–510 (1999).
15
ORIGINAL_ARTICLE
Activity Levels of Polonium-210 in Tobacco and Cigarette in Iran
Polonium-210 (210Po) is a natural contaminant of tobacco and its products. Due to its volatility and inherent adsorption properties, 210Po is one of the major potential sources of human exposure through smoking. This paper reports measurements on 210Po and 210Pb levels in domestic as well as imported tobacco to Iran through α-spectrometry technique. The fate of 210Po radionuclide has been also followed from tobacco farm through curing procedure in factory. The activity levels of 210Po in Iranian domestic and imported cigarettes is found to be on the average as 38.4±0.8 mBq/g with a range of 30.3-51.3mBq/g and 20.0±0.6mBq/g with a range of 18.6-21.7mBq/g, respectively. These levels are considerably higher than those reported in many other parts of the world. In the case of tobacco produced in Iranian northern province of Guilan, drying in closed compartments by fossil fuel and elevated inventories of 210Po in soil due to over application of phosphate-rich fertilizers seems to be the main causes of these elevated activity levels.
https://jonsat.nstri.ir/article_417_fa60ff806e58e27173509a9b6a95e463.pdf
2011-08-23
22
26
Polonium-210
Cigarette
tobacco
α-Spectrometry
Guilan
B
Ghanbar Moghaddam
1
دانشکده علوم، دانشگاه گیلان، صندوق پستی: 3489، رشت- ایران
LEAD_AUTHOR
M
Vahabi Moghaddam
2
دانشکده علوم، دانشگاه گیلان، صندوق پستی: 3489، رشت- ایران
AUTHOR
A.A
Fathi Vand
3
پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 1339-14155، تهران ـ ایران
AUTHOR
A. Savidou, K. Kehagia, K. Eleftheriadis, “Concentration levels of 210Pb and 210Po in dry tobacco leaves in Greece,” Journal of Environmetal Radioactivity, 85, 94-102 (2006).
1
Y.D. Parfenov, “Polonium-210 in the environment and in the human organism,” Atomic Energy Review, 12, 75–143 (1974).
2
B. Skwarzec, D.I. Struminska, J. Ulatowski, M. Golebiowski, “Determination and distribution of 210Po in tobacco plants from Poland,” Journal of Radioanalytical and Nuclear Chemistry, Vol. 250, No. 2, 319-322 (2001).
3
E.A. Martell, “Radioactivity of tobacco trichomes and insoluble cigarette smoke particles,” Nature, 249, 215-217 (1974).
4
R.L. Fleischer, “Aerosol particles on tobacco trichomes,” Nature, 250, 158-159 (1974).
5
Farsnews, www. farsnews.com (2007).
6
”کارنامهی آماری کشت توتون و خرید محصولات کشاورزی دخانی،“ شرکت دخانیات ایران، ادارهی کل امور کشاورزی (1380).
7
M. Aliabadi, et.al, “Determination of polonium-210 in iranian cigarettes, 2nd Int,” Conference on Nuclear Science and Technology, Shiraz University, Iran (2004).
8
A.C. Peres and G. Hiromoto, “Evaluation of 210Pb and 210Po in cigarette tobacco produced in Brazil,” J. Environmental Radioactivity 62, 115-119 (2002).
9
UNSCEAR 2000, Sources and Effects of Ionizing Radiation, United Nations Scientific Committee on the Effects of Atomic Radiation, Report to the General Assembly, United Nations, New York (2000).
10
”سالنامه آماری گیلان،“ سازمان مدیریت و برنامهریزی استان گیلان (1380).
11
T.C. Tso, N.A. Mallden, L.T. Aexander, “Radium-226 and polonium-210 in leaf tobacco and tobacco soil,” Science, 146, 1043-1045 (1964).
12
D.R. Singh and S.R. Nikelani, “Measurement of polonium activity in Indian tobacco,” Health Physics, 31, 393–394 (1976).
13
ل. غلامزاده کلیشمی، ”سنجش موجودی oP210 در کودهای شیمیایی مورد استفاده در گیلان،“ پایاننامه کارشناسی ارشد، دانشگاه گیلان (1386).
14
C. Papastefanou, “Radiation dose from cigarette tobacco,” Radiation Protection Dosimetry, Vol. 123, No. 1, 68–73 (2007).
15
A.E.M. Khater, “Polonium-210 budgets in cigarette,” Journal of Environmental Radioactivity, 71, 33-41 (2004).
16
Mussalo-Rauhamaa and H. Jaakkola, “T. Plutonium-239, Pu and Po contents of tobacco and cigarette smoke,” Health Physics, 49(2), 269-301 (1985).
17
D.R. Singh, S.R. Nilekani, “Measurement of Polonium activity in Indian tobacco,” Health Physics, 31, 393-394 (1976).
18
S.N.A. Tahir and A.S. Alaamer, “Pb-210 concentrations in cigarettes tobaccos and radiation dose to the smokers,” Radiation Protection Dosimetry, 130(3), 389-391 (2008).
19
Batarekh, K. Teherani and D.K. “Determination of Polonium-210 in cigarettes from Syria,” J. Radioanal, Nucl. Chem. 117( 2), 75-80 (1987).
20
T. Karali, S. Olmez, G. Yener, “Study of spontaneous deposition of 210Po on various metals and application for activity assessment in cigarette smoke,” Appl. Radiat. Isot. 47(4), 409-411 (1996).
21
C.R. Hill, “Polonium-210 in man,” Nature, 208(5009), 423-428 (1965).
22
ORIGINAL_ARTICLE
Investigation of the Influent Concentration Effect on the Uranium Biosorption by Cystoseira Indica Brown Alga in a Packed Bed Column
In this paper, biosorption of uranium (VI) from aqueous solution by Cystoseira indica brown alga was studied in a continuous packed bed column. The experiments were performed at room temperature and pH 4. The uptake capacity of uranium ions was investigated by Ca-pretreated biomass in a flow rate of 2.3ml/min, superficial velocity of 1.3cm/min, and different influent concentrations. The results showed that by increasing the influent concentration from 30 to 120mg/l, despite increasing the uptake capacity from 266.61 to 371.39mg/g, leads to reduction of the metal removal percentage. The experimental breakthrough curves were analyzed using Thomas, Yoon & Nelson and dose-response models. The investigations showed that these models are suitable for the breakthrough curves prediction.
https://jonsat.nstri.ir/article_418_ae2ec5ce34f5110c28a5ebf21fce01ef.pdf
2011-08-23
27
36
Biosorption
Uranium
Packed Bed Column
Brown Alga
Modeling
M
Ghasemi
1
دانشکده مهندسی هستهای، دانشگاه شهید بهشتی، صندوق پستی: 1983963113، تهران ـ ایران
AUTHOR
A
Keshtkar
akeshtkar@aeoi.org.ir
2
پژوهشکده چرخه سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران ـ ایران
LEAD_AUTHOR
R
Dabbagh
rdabbagh@aeoi.org.ir
3
پژوهشکده علوم هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 836-14395، تهران ـ ایران
AUTHOR
S.J
Safdari
jsafdari@aeoi.org.ir
4
پژوهشکده چرخه سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران ـ ایران
AUTHOR
K. Naddafi, R. Nabizadeh, R. Saeedi, A.H. Mahvi, F. Vaezi, K. Yaghmaeian, A. Ghasri, S. Nazmara, “Biosorption of lead(II) and cadmium(II) by protonated Sargassum glaucescens biomass in a continuous packed bed column,” J. Hazard Mater, 147, 785-791 (2007).
1
F. Pagnanelli, A. Esposito, F. Veglio, “Multi-metallic modelling for biosorption of binary systems,” Water Res, 36, 4095-4105 (2002).
2
E. Valdman, L. Erijman, F.L.P. Pessoa, S.G.F. Leite, “Continuous biosorption of Cu and Zn by immobilized waste biomass Sargassum sp.,” Process Biochem, 36, 869–873 (2001).
3
Z. Aksu, “Determination of the equilibrium, kinetic and thermodynamic parameters of the batch biosorption of nickel(II) ions onto Chlorella vulgaris,” Process Biochem, 38, 89-99 (2002).
4
R. Dabbagh, H. Ghafourian, A. Baghvand, G.R. Nabi, H. Riahi, M.A. Ahmadi Faghih, “Bioaccumulation and biosorption of stable strontium and strontium-90 by Oscillatoria homogenea cyanobacterium,” J. Radioanal Nucl. Ch, 272, 53-597 (2007).
5
T.A. Davis, B. Volesky, A. Mucci, “A review of the biochemistry of heavy metal biosorption by brown algae,” Water Res, 37, 4311-4330 (2003).
6
M.W. Figueira, B. Volesky, V.S.T. Ciminelli, F.A. Roddick, “Biosorption of metals in brown seaweed biomass,” Water Res, 34, 196-204 (2000).
7
B. Benguella and H. Benaissa, “Cadmium removal from aqueous solutions by chitin: kinetic and equilibrium studies,” Water Res, 36, 2463-2474 (2002).
8
W. Ma and J.M. Tobin, “Development of multimetal binding model and application to binary metal biosorption onto peat biomass,” Water Res, 37, 3967-3977 (2003).
9
B. Volesky, “Detoxification of metal-bearing effluents: biosorption for the next century,” Hydrometallurgy, 59, 203–216 (2001).
10
J. Wang and C. Chen, “Biosorbents for heavy metals removal and their future,” Biotechnol Adv, 27, 195-226 (2009).
11
R. Senthilkumar, K. Vijayaraghavan, M. Thilakavathi, P.V. Iyer, M. Velan, “Seaweeds for the remediation of wastewaters contaminated with zinc(II) ions,” J. Hazard Mater, 136, 791-799 (2006).
12
R. Dabbagh, M. Ebrahimi, F. Aflaki, H. Ghafourian, M.H. Sahafipour, “Biosorption of stable cesium by chemically modified biomass of Sargassum glaucescens and Cystoseira indica in a continuous flow system,” J. Hazard Mater, 159, 354-357 (2008).
13
M.H. Khani, A.R. Keshtkar, M. Ghannadi, H. Pahlavanzadeh, “Equilibrium, kinetic and thermodynamic study of the biosorption of uranium onto Cystoseria indica algae,” J. Hazard Mater, 150, 612-618 (2008).
14
M.H. Khani, A.R. Keshtkar, B. Meysami, M.F. Zarea, R. Jalali, “Biosorption of uranium from aqueous solutions by nonliving biomass of marine algae Cystoseira indica,” Elec. J. Biotechnol, 9, 100-106 (2006).
15
M. Calero, F. Hernainz, G. Blazquez, G. Tenorio, M.A. Martin-Lara, “Study of Cr(III) biosorption in a fixed-bed column,” J. Hazard Mater, 171, 886-893 (2009).
16
K. Vijayaraghavan, J. Jegan, K. Palanivelu, M. Velan, “Removal of nickel(II) ions from aqueous solution using crab shell particles in a packed bed up-flow column,” J. Hazard Mater, 113, 223-230 (2004).
17
Z. Aksu, S.S. Cagatay, F. Gonen, “Continuous fixed bed biosorption of reactive dyes by dried Rhizopus arrhizus: Determination of column capacity,” J. Hazard Mater, 143, 362–371 (2007).
18
B. Volesky, “Sorption and Biosorption,” BV Sorbex, St. Lambert, Que., Inc., Canada, (2003).
19
Z. Aksu and F. Gonen, “Biosorption of phenol by immobilized activated sludge in a continuous packed bed: prediction of breakthrough curves,” Process Biochem, 39, 599-613 (2004).
20
Y.H. Yoon and J.H. Nelson, “Application of gas adsorption kinetics. I. A theoretical model for respirator cartridge service life,” Am Ind Hyg Assoc J, 45, 509-516 (1984).
21
V.J. Vilar, C.M. Botelho, J.M. Loureiro, R.A. Boaventura, “Biosorption of copper by marine algae Gelidium and algal composite material in a packed bed column,” Bioresour Technol, 99, 5830-5838 (2008).
22
S.S. Ahluwalia and D. Goyal, “Microbial and plant derived biomass for removal of heavy metals from wastewater,” Bioresour Technol, 98, 2257-2243 (2007).
23
R. Han, Y. Wang, W. Zou, Y. Wang, J. Shi, “Comparison of linear and nonlinear analysis in estimating the Thomas model parameters for methylene blue adsorption onto natural zeolite in fixed-bed column,” J. Hazard Mater, 145, 331–33 (2007).
24
G. Yan and T. Viraraghavan, “Heavy metal removal in a biosorption column by immobilized M. rouxii biomass,” Bioresour Technol, 78, 243-249 (2001).
25
ORIGINAL_ARTICLE
Gamma Radiation Exposure of Aircrew in Tehran-Bandarabbas Flights
Different researches have been performed on natural exposure of cosmic rays and their effects on the human health. Monitoring of cosmic derived gamma ray exposure of aircrews and passengers is the subject of the current study. In this paper, the controlable variations of the cosmic ray flux in the atmosphere and the cosmic radiation exposure at flight altitudes will be discussed. For this study, the exposure rates to gamma ray, in an energy range of 50keV-1.5MeV, for the Tehran-Bandarabbas air flights have been measured. The results show that the maximum dose rate at 3000ft (about 9km) is 15-20 times higher than on the ground base. Also, the dose rate for this pathway is about 1.87μSv/h which for 500 hours flights per year it is estimatal to be 935μSv. This number is less than human permissible dose rate of 1mSv/year.
https://jonsat.nstri.ir/article_419_3602958e0c70c4c015ffb292feaf7631.pdf
2011-08-23
37
40
Cosmic Rays
Gamma radiation
Exposure
Dose Rate
Radiation Effects
R
Gholipour Peyvandi
1
پژوهشکده چرخه سوخت هستهای، پژوهشگاه علوم و فنون هستهای، سازمان انرژی اتمی ایران، صندوق پستی: 8486-11365، تهران ـ ایران
LEAD_AUTHOR
G. Reitz, “Radiation environment in the stratosphere,” Radiat. Protect. Dos. 48(1), 5-20 (1993).
1
O. Brien, K. Friedberg, W. Duke, F.E. Snyder, L. Darden Jr, E.B. Sauer, H.H., “The exposure of aircraft crews to radiations of extraterrestrial origin,” Radiat. Protec. Dos. 45(1-4), 145-162 (1992).
2
P. Lantos, “The sun and its effects on the terrestrial environment,” Radiat. Protec. Dos. 48(1), 27-32 (1993).
3
M.K. Lim, “Cosmic rays: are air crew at risk?,” Occup. Environ. Med. 59, 428-433 (2002).
4
F. Spurny, T.S. Dachev, “Long-term monitoring of the onboard aircraft exposure level with a Si-diode bsed spectrometer,” Adv. Space. Res. 32(1), 53-58 (2003).
5
S. Mohler, “Galactic radiation exposure during commercial flights: Is there a risk?,” Canadian. Med. Associat. J. 168, 1157-1158 (2003).
6
K.B. Shaw, “Radiation exposure and high- altitude flight,” J. Radiol. Prot. 16(2), 987-991 (1996).
7
ORIGINAL_ARTICLE
Computation of Gap Conductance in Different Fuel Assemblies in
VVER-1000 Type Reactors
In this paper, a calculation for fresh fuels gap conductance at different axial lengths of fuel assemblies of the VVER-1000 type reactors has been made using two models of Calza-Bini and Relap5. By applying these two models, the dependency of the fuel outer surface temperature and the clad inner surface temperature of the gap conductance has been determined upon using following procedures: Coupling gap conductance model computer programming to obtain temperature at different axial lengths of the fuel and clad; and coupling gap conductance model to the COBRA-EN output code. The results of calculations and comparison with the FSAR results showed that the Relap5 model is less accurate than the Calza-Bini model. The Calza-Bini model agrees well with the FSAR results. By combining these two models, a new model with a better accuracy was proposed for the gap conductance.
https://jonsat.nstri.ir/article_420_5a2c4ab9fa0f2f4b625fac2081756e77.pdf
2011-08-23
41
49
VVER-1000
Fuel Assemblies
Gap Conductance
COBRA-EN Code
Calza-Bini Model
Fuel Rods
M
Rahgoshay
1
دانشکده فنی مهندسی، دانشگاه آزاد اسلامی واحد علوم و تحقیقات تهران، صندوق پستی: 775-14515، تهران ـ ایران
LEAD_AUTHOR
KH
Shokri
2
دانشکده فنی مهندسی، دانشگاه آزاد اسلامی واحد علوم و تحقیقات تهران، صندوق پستی: 775-14515، تهران ـ ایران
AUTHOR
Final Safety Report for BUSHEHR VVER-1000 Reactor Chapter 4, Ministry of Russian Federation of Atomic Energy (Atomenergoproekt), Moscow (2003).
1
N. Todress, M.S. Kazimi, “Nuclear system I,” Hemisphere Publishing Corporation, New York (1982).
2
ENEL Spa, “COBRA-EN Code System for Thermal-Hydraulic Transient Analysis of Light Water Reactor Fuel Assemblies and Core International,” Milano, Italy (1991).
3
M.M. El-WAKIL “Nuclear Heat Transport,” Copyright, by International Textbook Company (1971).
4
RELAP5/MOD3 CODE MANUAL-VOLUME I: CODE STRUCTURE, SYSTEM, MODELS, AND SOLUTION METHODS; March (1998).
5
ORIGINAL_ARTICLE
Modal Analysis of Spent Fuel Cask for WWER-1000 Reactors
The Spent Fuel Assemblies (SFAs) of WWER-1000 reactors are planned to be transported by special containers which are supposed to be designed in a manner to stand against vibrations and impacts in order to protect the spent fuel from any possible damage. The vibration opposition of these containers shall be far beyond the critical resonance, because the resonances about the natural frequency of the structure will cause the enhancement of its oscillation range and may end with its disintegration. Determination of the amounts of natural frequencies and their mode shape can be achieved by vibration analyzing methods. The amount of the natural frequency of any structure crucially depends on its shape, material and lean points as well as the amount of the loads and the type of these loads. Due to the fact that the Spent Fuel Casks used for transportation in nuclear power plants in Russian Federation are TK-13 type and the pieces of information released are negligible, the scientists in Russia are working on the design and analysis of a new type made up of composite Material. In the presented paper the cask of spent fuel of TK-13 is modeled by ANSYS® 10.0 and ten natural frequency modes have been calculated, followed by the comparison of this result with the composite cask.
https://jonsat.nstri.ir/article_421_ad3f3a7255cac76820603ee269e7953b.pdf
2011-08-23
50
54
Natural Frequency
Vibration Mode
WWER-1000 Reactor
Critical Resonance
Spent Fuel Transportation Cask
Composite
S.A
Azimfar
1
Nuclear Power Production and Development Co. of Irna, AEOI, P.O. Box: 19395-7484, Tehran - Iran
LEAD_AUTHOR
A.
Kazemi
2
Nuclear Power Production and Development Co. of Irna, AEOI, P.O. Box: 19395-7484, Tehran - Iran
AUTHOR
“Description of fresh and spent fuel storage at balakovo NPP-definitions for safety calculation,” Russian Research Center "Kurchatov Institute", (April 2007).
1
ANSYS, Inc., “ANSYS users guide for revision 10.0,” ANSYS, Inc., PA, USA (2006).
2
Bechtel/Parsons Brinkerhoff, Inc. November 1995. Memorial Tunnel Fire Ventilation Test Program, Comprehensive Test Report, Prepared for Massachusetts Highway Department and Federal Highway Administration.
3
NRC Docket Number 71-9225. Legal Weight Truck Transport(LWT) Packaging Safety (2001).
4
Conceptual project “Multipurpose universal CERMET-based for transportation and temporary storage of SNF from power reactor,” (2006).
5
Project No 2693 of the International Science and Technology Center “Production and research of cast cermet based on stainless steel and dioxide of depleted uranium as applied to use of it as protective material in designs of casks for spent nuclear fuel and radioactive wastes,” (2006).
6