Studies on the overall safety aspects during irradiation of TeO2 in the central thimble of the TRIGA research reactor

Huda, M.Q.; Islam, Mohammed Saiful; Rahman, Md. Mizanur; Haque, A.; Uddin, M.S.

doi:10.1016/j.anucene.2008.11.013

Cited by 5 publications

(7 citation statements)

References 5 publications

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“…A 3 MW TRIGA Mark II reactor was installed at the campus of Atomic Energy Research Establishment (AERE) of Bangladesh Atomic Energy Commission (BAEC) in Savar in 1986 [cf . 1,2]. It is a zirconium hydride moderated, light-water cooled and graphite (with Al cladding) reflected pulsing type reactor, designed for steady state operation at a thermal power of up *Author for correspondence (E-mail: md.shuzauddin@yahoo.com).…”

Section: Introductionmentioning

confidence: 99%

Fast neutron spectrum unfolding of a TRIGA Mark II reactor and measurement of spectrum-averaged cross sections: integral tests of differential cross sections of neutron threshold reactions

et al. 2013

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Summary The spectrum of fast neutrons having energies from 0.5 to 20 MeV in the core of the 3MW TRIGA Mark II reactor at Savar, Dhaka, Bangladesh, was unfolded by activating several metal foils to induce threshold nuclear reactions covering the whole spectrum, and then doing necessary iterative calculations utilizing the activation results and the code SULSA. The analysed shape of the spectrum in the TRIGA core was found to be similar to that of the pure 235U-fission spectrum, except for the energies between 0.5 and 1.5 MeV, where it was slightly higher than the fission spectrum. Spectrum-averaged cross sections were determined by integral measurements. The integral values measured in this work were compared with the recommended values for a pure fission spectrum as well as with the integrated data deduced from measured and evaluated excitation functions of a few reactions given in some data files. The good agreement between integral measurements and integrated data in case of well-investigated reactions shows that the fast neutron field at the TRIGA Mark II reactor can be used for validation of evaluated data of neutron threshold reactions.

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Section: Introductionmentioning

confidence: 99%

Fast neutron spectrum unfolding of a TRIGA Mark II reactor and measurement of spectrum-averaged cross sections: integral tests of differential cross sections of neutron threshold reactions

et al. 2013

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“…Using conventional analytical methods, and heat transfer correlations, one-dimensional stationery the state, taking into account the transfer of heat, can be two important modes, conduction and thermal convection, radiation mode does not take place because all the material contains no empty. after all made calculates the temperature in the sample MoO 3 is 380°C lower than the melting point and then followed a decreasing in material (quartz, aluminum channel) until the water with a temperature 40°C, after all made calculated using the equation explain we find almost equal temperature values the same value tested experimentally 24,27 the results were schematized in the figure 4.…”

Section: Methodsmentioning

confidence: 52%

“…Using the heat transfer equation based on the three heat transfer modes, the thermal study Molybdenum-99 production by irradiation of the target in the central thimble showed that the materials of the temperatures do not exceed their corresponding melting points, and as was confirmed by the Figure shown in Figure 2 [22][23][24] .…”

Section: Resultsmentioning

confidence: 78%

“…So, the activity equal eq. Figure 1 represents the design of the capsule used for the irradiation of MoO 3 (2.54 cm radius and height of 15.24 cm) 24 , the target will be sealed in a quartz bulb as the first barrier to prevent an exothermic reaction between al and MoO 3 , empty space containing the product gas during irradiation. To prevent the gap between the quartz and the aluminum layer the target will be surrounded by an aluminum foil at the end to avoid any mechanical risk and facilitate the transfer of heat.…”

Section: Methodsmentioning

confidence: 99%

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Toward for production of Molybdenum-99 by irradiation of MoO3 target in a neutron flux

Didi

Dadouch

Jaï

et al. 2018

Bangladesh J Med Sci

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Background: Molybdenum- 99 is a parent isotope of Technetium-99m (99mTc) as intermediate to diagnosis and radiation treatment. This production is made according to irradiation of Molybdenum-98 with thermal neutrons. The cycle comprises a complex of MoO3 or the percentage of Mo-98 is 24.13%, this compressed mixture in an irradiation capsule of aluminum; the latter is disposed in the central thimble of a nuclear reactor so that the thermal neutron flux is at a maximum in order to generate 98Mo to 99Mo by nuclear reaction of (n, γ) where the crosssection of molybdenum is (0.13 ± 0.0013) barn.Method: The purpose of this study is to validate of MoO3 target that will be used for the production of Molybdenum-99 in the central thimble irradiation position of the TRIGA Mark II research reactor at CNESTEN (Morocco National Center for Nuclear Energy, Sciences and Techniques), The thermal neutron flux used for activity calculation of Mo-99 used reactor of research TRIGA Mark-II is 3.1 1011 n/cm²s at 250 KW, 2.4E+13 n/cm2s at 1.1 MW and 3.01 1013n/cm²s at 2MW, we are using Fortran-90 code for calculate the activity.Result: The result’s finding was validated by other studies.Bangladesh Journal of Medical Science Vol.17(4) 2018 p.567-572

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“…In the past, there were several researches related to the safety analyses of the radioisotope (RI) target insertion using uncoupled neutronic and thermal-hydraulic (N/TH) analytical tools [5][6][7][8][9][10]. The use of a coupled N/TH analytical tool is expected to improve the accuracy of the analysis results since the code simulates the real operation conditions and transients of a reactor.…”

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confidence: 99%

Neutronic and Thermal-Hydraulic Safety Analysis for the Optimization of the Uranium Foil Target in the RSG-GAS Reactor

2016

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Studies on the overall safety aspects during irradiation of TeO2 in the central thimble of the TRIGA research reactor

Cited by 5 publications

References 5 publications

Fast neutron spectrum unfolding of a TRIGA Mark II reactor and measurement of spectrum-averaged cross sections: integral tests of differential cross sections of neutron threshold reactions

Fast neutron spectrum unfolding of a TRIGA Mark II reactor and measurement of spectrum-averaged cross sections: integral tests of differential cross sections of neutron threshold reactions

Toward for production of Molybdenum-99 by irradiation of MoO3 target in a neutron flux

Neutronic and Thermal-Hydraulic Safety Analysis for the Optimization of the Uranium Foil Target in the RSG-GAS Reactor

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