ORIGINAL_ARTICLE
Measurement of naturally occurring radioactive materials concentration in Tehran’s water using Gamma spectrometry
The concentration of naturally occurring radioactive materials (NORM) in surface water and irrigation wells is measured using gamma ray spectrometry by HPGe detector. Measurement was carried out for samples that were collected over seventeen points in Tehran city and its suburbs. The samples were prepared in compliance with the principles from irrigation wells of city. The specific radioactivity of Ra-226, Th-232 and K-40 were measured and the results from different locations covered a range with the minimum being below "minimum detectable activity" up to maximum of 4.04, and 6.85 and 4.7 Bq per liter of water, respectively. The accumulation of radioactive materials in the samples from southern areas of Tehran was more than that of central areas. Also, concentration of Ra-226 in all the samples was less than the Derived Release Limit of Canada and Environmental Protection Agency standard threshold.
https://rpe.kntu.ac.ir/article_57882_28456f715939469b56483ca8f76c96b3.pdf
2020-01-01
1
5
10.22034/rpe.2020.57882
Naturally radioactive materials
Gamma ray spectrometry
HPGe detector
Tehran's water
Mehrnaz
Zehtabvar
1
Department of Nuclear Engineering, Faculty of Engineering, Islamic Azad University, Science and Research Branch, Tehran, Iran.
AUTHOR
Dariush
Sardari
2
Department of Medical Radiation Engineering, Faculty of Engineering, Islamic Azad University, Science and Research Branch, Tehran, Iran.
LEAD_AUTHOR
Gholamreza
Jahanfarnia
3
Department of Nuclear Engineering, Faculty of Engineering, Islamic Azad University, Science and Research Branch, Tehran, Iran.
AUTHOR
Agbalagba, E. O. and Onoja, R. A. (2011). Evaluation of natural radioactivity in soil, sediment and water samples of Niger Delta (Biseni) flood plain lakes, Nigeria. Journal of Environmental Radioactivity, 102(7):667–671.
1
Ahmed, N. K. (2004). Natural radioactivity of ground and drinking water in some areas of upper Egypt. Turkish Journal of Engineering and Environmental Sciences, 28(6):345–354.
2
Aksoy, A., Al-Jarallah, M., and Al-Haddad, M. N. (2002). Natural radioactivity in the scale of water well pipes. Journal of Environmental Radioactivity, 61(1):33–40.
3
Bou-Rabee, F., Al-Zamel, A. Z., Al-Fares, R. A., et al. (2009). Technologically enhanced naturally occurring radioactive materials in the oil industry (TENORM). Nukleonika, 54:3–9.
4
Cevik, U., Damla, N., Karahan, G., et al. (2005). Natural radioactivity in tap waters of Eastern Black Sea region of Turkey. Radiation Protection Dosimetry, 118(1):88–92.
5
Diab, H. M., Nouh, S. A., Hamdy, A., et al. (2008). Evaluation of natural radioactivity in a cultivated area around a fertilizer factory. Journal of Nuclear and Radiation Physics, 3(1):53–62.
6
Fatima, I., Zaidi, J. H., Arif, M., et al. (2006). Measurement of natural radioactivity in bottled drinking water in Pakistan and consequent dose estimates. Radiation Protection Dosimetry, 123(2):234–240.
7
Godoy, J. M. and Godoy, M. L. (2006). Natural radioactivity in Brazilian groundwater. Journal of Environmental Radioactivity, 85(1):71–83.
8
IAEA (1989). Measurement of Radionuclides in Food and the Environment, A guide book. Technical Report Series No. 295, IAEA, Vienna.
9
Inoue, M., Yoshida, K., Minakawa, M., et al. (2012). Spatial variations of Ra-226, Ra-228, Cs-137, and Th-228 activities in the southwestern Okhotsk Sea. Journal of Environmental Radioactivity, 104:75–80.
10
Todorovic, N., Nikolov, J., Forkapic, S., et al. (2012). Public exposure to radon in drinking water in Serbia. Applied Radiation and Isotopes, 70(3):543–549.
11
UNSCEAR (2000). Sources and effects of ionizing radiation. United Nations Scientific Committee of Atomic Radiation report, pages 453–487.
12
Yussuf, N. M., Hossain, I., and Wagiran, H. (2012). Natural radioactivity in drinking and mineral water in Johor Bahru (Malaysia). Scientific Research and Essays, 7(9):1070–1075.
13
Zare, M. R., Kamali, M., Omidi, Z., et al. (2015). Evaluation of natural radioactivity content in high-volume surface water samples along the northern coast of Oman Sea using
14
portable high-resolution gamma-ray spectrometry. Journal of Environmental Radioactivity, 144:134–139.
15
ORIGINAL_ARTICLE
Introducing a novel FDG synthesis method in Iran based on alkaline hydrolysis
18F-FDG PET/CT is commonly used for evaluation and diagnostic of many types of cancer, such as; tumor diagnosis, treatment monitoring, and radiation therapy planning. Accurate diagnostic is needed in meticulous patient preparation, including restrictions of diet and activity and management of blood glucose levels in diabetic patients, as well as an awareness of the effect of medications and environmental conditions. All of these conditions play important roles toward obtaining good-quality images, which are essential for accurate interpretation. This article introduces the new synthesis and quality control method for obtaining the best quality FDG which is used as radiopharmaceutical. All the reactions are carried out and completed in one reaction vessel without any replacement. The paper is including details of synthesis, quality control and transportation step. It is the first time that the alkaline FDG synthesis is introducing by details in Iran.
https://rpe.kntu.ac.ir/article_57883_e9a35a4728a0959ba7c83509d60a1196.pdf
2020-01-01
7
11
10.22034/rpe.2020.57883
Alkaline Hydrolysis
Synthesis
FDG=[18F]Fluorodeoxyglucose
Parviz
Ashtari
1
Application Radiation Research School, Nuclear Science and Technology Research Institute, Tehran, Iran.
LEAD_AUTHOR
ACR-SPR (2014). ACR-SPR practice parameter for performing FDG-PET/CT in oncology. Reston, VA: American College of Radiology.
1
Beyer, T., Czernin, J., and Freudenberg, L. S. (2011). Variations in clinical PET/CT operations: results of an international survey of active PET/CT users. Journal of Nuclear Medicine, 52(2):303–310.
2
Boellaard, R., O’Doherty, M. J., Weber, W. A., et al. (2010). FDG PET and PET/CT: EANM procedure guidelines for tumour PET imaging: version 1.0. European Journal of Nuclear Medicine and Molecular Imaging, 37(1):181.
3
Delbeke, D., Coleman, R. E., Guiberteau, M. J., et al. (2006). Procedure guideline for tumor imaging with 18F-FDG
4
PET/CT 1.0. Journal of Nuclear Medicine, 47(5):885–895. Graham, M. M., Badawi, R. D., andWahl, R. L. (2011). Variations in PET/CT methodology for oncologic imaging at US academic medical centers: an imaging response assessment team survey. Journal of Nuclear Medicine, 52(2):311–317.
5
IAEA (2012). Cyclotron Produced Radionuclides: Operation and Maintenance of Gas and Liquid Targets. Radioisotopes and Radiopharmaceuticals Series No. 4.
6
IAEA-TECDOC-1310 (2002). Optimization of synthesis and quality control procedures for the preparation of F-18 and
7
I-123 labelled peptides for nuclear medicine. Jacene, H. A., Leboulleux, S., Baba, S., et al. (2009). Assessment of interobserver reproducibility in quantitative 18FFDG PET and CT measurements of tumor response to therapy. Journal of Nuclear Medicine, 50(11):1760–1769.
8
Shankar, L. K., Hoffman, J. M., Bacharach, S., et al. (2006). Consensus recommendations for the use of 18F-FDG PET as an indicator of therapeutic response in patients in National Cancer Institute Trials. Journal of Nuclear Medicine, 47(6):1059–1066.
9
Surasi, D. S., Bhambhvani, P., Baldwin, J. A., et al. (2014). 18F-FDG PET and PET/CT patient preparation: a review of the literature. Journal of Nuclear Medicine Technology, 42(1):5–13.
10
ORIGINAL_ARTICLE
A Geant4 study on dosimetric comparison between three kinds of radioactive esophageal stents to be used in treatment of advanced esophageal cancers
Utilizing radioactive stents is a usual method for treatment of advanced esophageal cancer. It is necessary to investigate the dose distribution of radioactive esophageal stents before the clinical use. This study presents a dosimetric comparison between three radioactive esophageal stents: I-125 seed-loaded stent, iodine-eluting stent and double-layered iodine-eluting stent. Depth-dose and angular dose distributions were carried out using Geant4 toolkit. Moreover, the effect of interval distance between two adjacent seeds on the dose distribution was investigated. Esophageal stents loaded with I-125 seeds seems to be better than iodine-eluting stents, with the distance less than 15 mm between two adjacent seeds.
https://rpe.kntu.ac.ir/article_57884_1402e5658ec4b5a1e0cc77a993af45dd.pdf
2020-01-01
13
18
10.22034/rpe.2020.57884
Advanced esophageal cancer
Radioactive stent
Brachytherapy
Dosimetry
Geant4
Payam
Rafiepour
1
Department of Nuclear Engineering and Physics, Amirkabir University of Technology, Tehran, Iran
LEAD_AUTHOR
Shahab
Sheibani
2
Nuclear Science Research School, Nuclear Science and Technology Research Institute NSTRI, Tehran, Iran
AUTHOR
Daryiush
Rezaey Uchbelagh
3
Department of Nuclear Engineering and Physics, Amirkabir University of Technology, Tehran, Iran
AUTHOR
Hossein
Poorbaygi
4
Nuclear Science Research School, Nuclear Science and Technology Research Institute NSTRI, Tehran, Iran
AUTHOR
Agostinelli, S., Allison, J., Amako, K. A., et al. (2003). GEANT4–a simulation toolkit. Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment, 506(3):250-303.
1
Chiu-Tsao, S.-T., Schaart, D. R., Soares, C. G., et al. (2007). Dose calculation formalisms and consensus dosimetry parameters for intravascular brachytherapy dosimetry: Recommendations of the AAPM Therapy Physics Committee Task Group No. 149. Medical Physics, 34(11):4126–4157.
2
Chu, J., Jin, J., Ni, S., et al. (2008). Radiation field feature of 188Re esophageal stent. Nuclear Medicine Communications, 29(5):462–464.
3
Dai, Z., Zhou, D., Hu, J., et al. (2013). Clinical application of iodine-eluting stent in patients with advanced esophageal
4
cancer. Oncology Letters, 6(3):713–718.
5
Gaspar, L. E., Nag, S., Herskovic, A., et al. (1997). American Brachytherapy Society (ABS) consensus guidelines for brachytherapy of esophageal cancer. International Journal of Radiation Oncology Biology Physics, 38(1):127–132.
6
Geant4 (2017). Geant4 physics reference manual (online available). http://geant4.web. cern.ch/geant4/UserDocumentation/UsersGuides/PhysicsReferenceManual/fo/PhysicsReferenceManual.pdf.
7
Guo, J.-H., Teng, G.-J., Zhu, G.-Y., et al. (2008). Selfexpandable esophageal stent loaded with 125I seeds: initial experience in patients with advanced esophageal cancer. Radiology, 247(2):574–581.
8
Kim, E. S., Jeon, S. W., Park, S. Y., et al. (2009). Comparison of double-layered and covered Niti-S stents for palliation
9
of malignant dysphagia. Journal of Gastroenterology and Hepatology, 24(1):114–119.
10
Lin, L., Wang, J., Yang, R., et al. (2015). An Experimental Modal Investigation of the Dosimetry Parameters for Self-Expandable Esophageal Stent Loaded With I-125 Seeds. Brachytherapy, 14:S66–S67.
11
Liu, N., Liu, S., Xiang, C., et al. (2014). Radioactive selfexpanding stents give superior palliation in patients with unresectable cancer of the esophagus but should be used with caution if they have had prior radiotherapy. The Annals of Thoracic Surgery, 98(2):521–526.
12
Lohrabian, V., Sheibani, S., Aghamiri, M. R., et al. (2013). Determination of dosimetric characteristics of irseed 125I brachytherapy source. Iranian Journal of Medical Physics, 10(2):109–117.
13
Mariette, C., Piessen, G., and Triboulet, J.-P. (2007). Therapeutic strategies in esophageal carcinoma: role of surgery and other modalities. The Lancet Oncology, 8(6):545–553.
14
Napier, K. J., Scheerer, M., and Misra, S. (2014). Esophageal cancer: A Review of epidemiology, pathogenesis, staging workup and treatment modalities. World Journal of Gastrointestinal Oncology, 6(5):112.
15
Nath, R., Amols, H., Coffey, C., et al. (1999). Intravascular brachytherapy physics: report of the AAPM Radiation Therapy Committee Task Group No. 60. Medical Physics, 26(2):119–152.
16
Rivard, M. J., Coursey, B. M., DeWerd, L. A., et al. (2004). Update of AAPM Task Group No. 43 Report: A revised AAPM protocol for brachytherapy dose calculations. Medical Physics, 31(3):633–674.
17
Won, J. H., Lee, J. D., Wang, H. J., et al. (2002). Selfexpandable covered metallic esophageal stent impregnated with beta-emitting radionuclide: an experimental study in canine esophagus. International Journal of Radiation Oncology Biology Physics, 53(4):1005–1013.
18
Won, J. H., Lee, J. D., Wang, H. J., et al. (2005). Effects of a holmium-166 incorporated covered stent placement in normal canine common bile ducts. Journal of Vascular and Interventional Radiology, 16(5):705–711.
19
Yao, L.-H., Wang, J.-J., Shang, C., et al. (2017). In vitro Dosimetric Study of Biliary Stent Loaded with Radioactive 125I Seeds. Chinese Medical Journal, 130(9):1093.
20
Zhen, C., Ya-hong, C., andWei, L. (2014). Preparation of 125I Radioactive Covered Metal Stent. Tongweisu, 27(2):109–115.
21
Zhongmin, W., Xunbo, H., Jun, C., et al. (2012). Intraluminal radioactive stent compared with covered stent alone for the treatment of malignant esophageal stricture. Cardiovascular and Interventional Radiology, 35(2):351–358.
22
Zhu, H.-D., Guo, J.-H., Mao, A.-W., et al. (2014). Conventional stents versus stents loaded with iodine-125 seeds for the treatment of unresectable oesophageal cancer: a multicentre, randomised phase 3 trial. The Lancet Oncology, 15(6):612–619.
23
ORIGINAL_ARTICLE
Three-dimensional solution of the forward and adjoint neutron diffusion equation using the generalized least squares finite element method
Numerical solution of the multi-group static forward and adjoint neutron diffusion equation (NDE) using the Finite Elements Method (FEM) is investigated in detail. A finite element approach based on the generalized least squares method is applied for the spatial discretization of the NDE in 3D-XYZ geometry. A computer code called GELES was also developed based on the described methodology covering linear or quadratic tetrahedral elements generated via the mesh generator for an arbitrary shaped system. A number of test cases are also studied to validate the proposed approach. Moreover, to assess the output dependency to the number of elements, a sensitivity analysis is carried out at the end.
https://rpe.kntu.ac.ir/article_57885_71a444fdd987dd8f87e77a18249cbddc.pdf
2020-01-01
19
27
10.22034/rpe.2020.57885
Neutron Diffusion Equation
Adjoint Flux
Generalized Least Squares
Finite Element Method
Farahnaz
Saadatian Derakhshandeh
1
MASNA engineering company, P.O. Box 1439951113, Tehran, Iran
LEAD_AUTHOR
Ackroyd, R. (1986a). A finite element method for diffusion theory embracing nodal and difference methods. Progress in Nuclear Energy, 18(1-2):7–20.
1
Ackroyd, R. T. (1986b). Generalized least squares as a generator of variational principles and weighted residual methods for FEM transport methods. Progress in Nuclear Energy, 18(1-2):45–62.
2
Bell, G. I. and Glasstone, S. (1970). Nuclear Reactor Theory. Technical report, Division of Technical Information, US Atomic Energy Commission. Cavdar, S. and Ozgener, H. A. (2004). A finite element boundary element hybrid method for 2-D neutron diffusion calculations. Annals of Nuclear Energy, 31(14):1555–1582.
3
Center, A. C. (1977). ANL Benchmark Book-Report ANL-7416. Argonne National Laboratory, Argonne, IL.
4
Duderstadt, J. J. and Hamilton, L. J. (1976). Nuclear Reactor Analysis, volume 1. Wiley New York. H´ebert, A. (2008). A Raviart–Thomas–Schneider solution of the diffusion equation in hexagonal geometry. Annals of Nuclear Energy, 35(3):363–376.
5
H´ebert, A., Sekki, D., and Chambon, R. (2013). A User Guide for DONJON Version4. ´Ecole Polytechnique de Montr´eal Montr´eal QC, Canada, Tech. Rep. IGE-300.
6
Kang, C. M. and Hansen, K. F. (1973). Finite element methods for reactor analysis. Nuclear Science and Engineering, 51(4):456–495.
7
Kolev, N., Lenain, R., and Magnaud, C. (1999). AER Benchmark Specification Sheet. Test ID.: AER–FCM, 101. Lamarsh, J. R. (1975). Introduction to Nuclear Engineering. Lewis, E. E. (1981). Finite element approximation to the even-parity transport equation. In Advances in Nuclear Science and Technology, pages 155–225. Springer.
8
McConnell, A. J. (1951). The hypercircle method of approximation for a system of partial differential equations of the second order. In Proceedings of the Royal Irish Academy.
9
Section A: Mathematical and Physical Sciences, volume 54, pages 263–290. JSTOR.
10
Schulz, G. (1996). Solutions of a 3D VVER-1000 Benchmark. In Proc. 6-th Symposium of AER on VVER Reactor Physics and Safety, Kirkkonummi, Finland.
11
Wang, Y., Bangerth, W., and Ragusa, J. (2009). Threedimensional h-adaptivity for the multigroup neutron diffusion equations. Progress in Nuclear Energy, 51(3):543–555.
12
Zienkiewicz, O. C. and Taylor, R. L. (2005). The finite element method for solid and structural mechanics. Butterworth heinemann
13
ORIGINAL_ARTICLE
Calculation of dose uniformity ratio in irradiation cell of GC-220 using analytical method based on multipole moment expansion
In this paper, dose uniformity ratio in irradiation cell of GC-220 is specifiedutilizing an analytical method based on the multipole moment expansion. In this method, the values of monople, dipole and quadrupole moments for source arrangements of GC-220 are calculated by numerical integrating. Appling these values, the dose uniformity ratio in the irradiation cell of GC-220 is calculated equal to 1.92. Monte Carlo simulation is applied to validate calculations. There is a relative difference about 12% between the results obtained from the analytical calculation and Monte Carlo simulation, which confirm the used method. In comparison with Monte Carlo methods, this method is not time consuming, so, this method can be used for the conceptual designing and the source load planning of irradiators.
https://rpe.kntu.ac.ir/article_57886_e0e15fa50bd27b21ce8cf778fe89cba4.pdf
2020-01-01
29
32
10.22034/rpe.2020.57886
Dose Uniformity Ratio
Mutipole Moment Expansion
Monte Carlo Method
Gamma Cell 220
Source Load Planning
Peiman
Rezaeian
1
Radiation Applications Research School, Nuclear Science and Technology Research Institute, AEOI, PO Box 11365-3486, Tehran, Iran
AUTHOR
Vahideh
Ataenia
2
Radiation Applications Research School, Nuclear Science and Technology Research Institute, AEOI, PO Box 11365-3486, Tehran, Iran
AUTHOR
Sepideh
Shafiei
3
Physics and Accelerators Research School, Nuclear Science and Technology Research Institute, AEOI, PO Box 11365-3486, Tehran, Iran
AUTHOR
Akhavan, A., Sheikh, N., Khoylou, F., et al. (2014). Synthesis of antimicrobial silver/hydroxyapatite nanocomposite by gamma irradiation. Radiation Physics and Chemistry, 98:46–50.
1
Briesmeister, J. F. et al. (2000). MCNP4 A Monte Carlo N Particle Transport Code System. Contributed by Los Alamos National Laboratory, Los Alamos, New Mexico.
2
Chu, R. D. H. (1990). Dosimetry studies to determine optimum processing parameters to minimize dose variations in non-uniform product. International Journal of Radiation Applications and Instrumentation. Part C. Radiation Physics and Chemistry, 35(4-6):841–844.
3
Cummins, D. O. and Delaney, C. F. G. (1961). Design studies for a Cs-137 irradiator. The International Journal of Applied Radiation and Isotopes, 10(2-3):106–111.
4
Farah, K., Jerbi, T., Kuntz, F., et al. (2006). Dose measurements for characterization of a semi-industrial cobalt-60 gamma-irradiation facility. Radiation Measurements, 41(2):201–208.
5
Gual, M. R., Batista, A. d. S. M., Pereira, C., et al. (2013). Dose rate distribution of the Gamma Beam-127 irradiator using MCNPX code. International Nuclear Atlantic Conference; Recife, PE (Brazil).
6
Kadri, O., Gharbi, F., and Farah, K. (2005). Monte Carlo improvement of dose uniformity in gamma irradiation processing using the GEANT4 code. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 239(4):391–398.
7
Oliveira, C. and Salgado, J. (2001). Isodose distributions and dose uniformity in the portuguese gamma irradiation facility calculated using the MCNP code. Radiation Physics and Chemistry, 61(3):791–793.
8
Raisali, G. R., Sohrabpour, M., and Hadjinia, A. (1990). A computer code for dose rate mapping of gamma irradiators.
9
International Journal of Radiation Applications and Instrumentation. Part C. Radiation Physics and Chemistry, 35(4-6):831–835.
10
Rezaeian, P., Ataenia, V., and Shafiei, S. (2017). An analytical method based on multipole moment expansion to calculate the flux distribution in Gammacell-220. Radiation Physics and Chemistry, 141:339–345.
11
Sharpe, P. H. G., Sephton, J. P., and Chu, R. D. (2000). Real time dosimetry measurements at an industrial irradiation plant. Radiation Physics and Chemistry, 57(3):687–690.
12
Solanki, R. B., Prasad, M., Sonawane, A. U., et al. (2012). Probabilistic safety assessment for food irradiation facility. Annals of Nuclear Energy, 43:123–130.
13
Soliman, Y. S., Beshir, W. B., Abdel-Fattah, A. A., et al. (2013). Dosimetric studies for gamma radiation validation of medical devices. Applied Radiation and Isotopes, 71(1):21–28.
14
Vandana, S., Shaiju, V. S., Sharma, S. D., et al. (2011). Dosimetry of gamma chamber blood irradiator using Gafchromic EBT film. Applied Radiation and Isotopes, 69(1):130–135.
15
ORIGINAL_ARTICLE
Reduction of radiation exposure probability at Tehran research reactor equipped with a second shutdown system
A second shutdown system (SSS) is designed for the Tehran Research Reactor (TRR) completely independent and diverse from the existing First Shutdown System (FSS). Given limitations, specifications, and requirements of the reactor, the design of SSS is based on the injection of liquid neutron absorber. The plan has the ability to satisfy the major criterion of required negative reactivity worth, to transfer the reactor to subcritical state in needed time, with necessary shutdown margin and for the required duration. Design calculations are performed using the stochastic code MCNPX2.6.0, deterministic code PARET and Pipe Flow Expert software. The ORIGEN2 code and HotSpot health physics code are also used for simulation of environmental pollution release. The SSS chambers cause a decrease of about 5% and 15% in total and thermal neutron flux, respectively. To demonstrate the SSS role in enhancing reactor safety, the probable accident of core meltdown is investigated. As a consequence of this accident, the radioactive pollution in and out of reactor containment is released. Without existing the SSS and in case of failure of FSS, the residents within 58000 m2 of the reactor perimeter would receive about 1 mSv which is more than the annual limit of absorbed dose for the community.
https://rpe.kntu.ac.ir/article_57887_06b31557b8cac998728cfa370544f9d2.pdf
2020-01-01
33
38
10.22034/rpe.2020.57887
Tehran research reactor
Safety
Second shutdown system
MCNPX code
ORIGEN2 code
PARET code
HotSpot code
Ehsan
Boustani
1
Nuclear Science and Technology Research Institute (NSTRI), Reactor and nuclear safety school, Tehran, Iran
AUTHOR
Samad
Khakshournia
2
Nuclear Science and Technology Research Institute (NSTRI), Accelerator and physics school, Tehran 14399-51113, Iran
AUTHOR
AEOI (2009a). Logbook of Tehran Research Reactor No. 38. Atomic Energy Organization of Iran.
1
AEOI (2009b). Safety Analysis Report for Tehran Research Reactor. Atomic Energy Organization of Iran.
2
ARPANSA (2001). Regulatory Assessment Principles for Controlled Facilities. Australian Radiation Protection and Nuclear Safety Agency, RB-STD-42-00 Rev 1.
3
Boffie, J., Odoi, H. C., Akaho, E. H. K., et al. (2012). Design of an additional safety rod for Ghana Research Reactor-1 using MCNP5 code. Nuclear Engineering and Design, 245:13–18.
4
Bond, D. S., Franklin, S. J., Chapman, N. J., et al. (2005). Development of a diverse secondary shutdown system for a low power research reactor. In Research reactor utilization, safety, decommissioning, fuel and waste management. Posters of an international conference.
5
B¨oning, K. and Blombach, J. (1995). Design and safety features of the planned compact core research reactor FRM-II. Technical report.
6
Boustani, E. and Khakshournia, S. (2017). Enhancing Tehran Research Reactor safety through a Second Shutdown System: A probabilistic safety assessment. Progress in Nuclear Energy, 100:380–388.
7
Boustani, E., Khakshournia, S., and Khalafi, H. (2016). A pragmatic approach towards designing a second shutdown system for Tehran research reactor. Nuclear Technology and Radiation Protection, 31(1):28–36.
8
Dalle, H. M., de Mattos, J. R. L., and Dias, M. S. (2013). Enriched gadolinium Burnable Poison for PWR Fuel–Monte Carlo Burnup Simulations of Reactivity. In Current Research in Nuclear Reactor Technology in Brazil and Worldwide. In-Tech.
9
Daxesoft-Ltd (2010). Pipe flow expert user guide. https://www.pipeflow.com/public/documents/ PipeFlowExpertUserGuide.pdf.
10
Homann, S. G. (2009). HOTSPOT health physics codes for the PC, Version 2.07, Users Guide. Technical report, Lawrence Livermore National Lab., CA (United States).
11
IAEA (1991). Research reactor core conversion guidebook, TEC-DOC 643. 2, Vienna.
12
IAEA (1999). Basic Safety Principles for Nuclear Power Plants. INSAG-12, 75-INSAG-3 Rev. 1.
13
IAEA (2008). Derivation of the Source Term and Analysis of the Radiological Consequences of Research Reactor. Safety report series No. 53.
14
IAEA (2009). Safey assessment of facilities and activities, General safety requirements. No. GSR part 4.
15
INVAP, M. (2006). 3.0. Neutronic, Thermal Hydraulic and Shielding Calculations on Personal Computers. Nuclear Engineering Division, INVAP, Bariloche.
16
Kim, S.-J. (2006). The OPAL (open pool Australian light water) reactor in Australia. Nuclear Engineering and Technology, 38(5):443–448.
17
Lintereur, A. T., Ely, J. H., Kouzes, R. T., Rogers, J. L., and Siciliano, E. R. (2012). Boron-10 lined proportional counter model validation. In Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC), 2012 IEEE, pages 4290–4295. IEEE.
18
Ludwig, S. B. and Croff, A. G. (2002). ORIGEN2. 2–Isotope Generation and Depletion Code Matrix Exponential Method. Oak Ridge National Laboratory.
19
Vanmaercke, S., Van den Eynde, G., Tijskens, E., et al. (2012). Design of a complementary scram system for liquid metal cooled nuclear reactors. Nuclear Engineering and Design, 243:87–94.
20
Waters, L. S. et al. (2002). MCNPX users manual (Accesed in Apr 15, 2012). http://mcnpx.lanl.gov/opendocs/ versions/v230/MCNPX_2.3.0_Manual.pdf.
21