Wyniki wyszukiwania - BazTech

1

Investigation of 99Mo potential production via UO2SO4 liquid target irradiation in a 5 MW nuclear research reactor

Gholamzadeh Z., Mirvakili S. M., Davari A., Alizadeh M., Joz-Vaziri A.

Nukleonika

|

2017

|

Vol. 62, No. 1

37--45

EN

The activation method for 99Mo production in comparison to fi ssionable target irradiation in research reactors is less preferable. Therefore, 99Mo yield using UO2SO4 samples was theoretically investigated. Computational results revealed admirable potential of the liquid samples for 99Mo production. Low-concentrated uranyl sulphate samples could easily be handled by the irradiation box. The sample geometry optimization improves thermal hydraulic conditions and production yield. The optimized geometry including only 0.12 g 235U produced 57Ci99Mo at end-of-irradiation (EOI) with a temperature peak of 72°C during the irradiation.

2

Burn-up calculation of different thorium-based fuel matrixes in a thermal research reactor using MCNPX 2.6 code

Gholamzadeh Z., Feghhi S. A. H., Soltani L., Rezazadeh M, Tenreiro C., Joharifard M.

Nukleonika

|

2014

|

Vol. 59, No. 4

129--136

EN

Decrease of the economically accessible uranium resources and the inherent proliferation resistance of thorium fuel motivate its application in nuclear power systems. Estimation of the nuclear reactor’s neutronic parameters during different operational situations is of key importance for the safe operation of nuclear reactors. In the present research, thorium oxide fuel burn-up calculations for a demonstrative model of a heavy water- -cooled reactor have been performed using MCNPX 2.6 code. Neutronic parameters for three different thorium fuel matrices loaded separately in the modelled thermal core have been investigated. 233U, 235U and 239Pu isotopes have been used as fi ssile element in the thorium oxide fuel, separately. Burn-up of three different fuels has been calculated at 1 MW constant power. 135X and 149Sm concentration variations have been studied in the modelled core during 165 days burn-up. Burn-up of thorium oxide enriched with 233U resulted in the least 149Sm and 135Xe productions and net fi ssile production of 233U after 165 days. The negative fuel, coolant and void reactivity of the used fuel assures safe operation of the modelled thermal core containing (233U-Th) O2 matrix. Furthermore, utilisation of thorium breeder fuel demonstrates several advantages, such as good neutronic economy, 233U production and less production of long-lived α emitter high radiotoxic wastes in biological internal exposure point of view.

3

Thick zinc electrodeposition on copper substrate for cyclotron production of 64Cu

Sadeghi M., Amiri M., Rowshanfarzad P., Gholamzadeh Z., Ensaf M.

Nukleonika

|

2008

|

Vol. 53, No. 4

155-160

EN

Zinc-68 electrodeposition on a copper substrate was investigated for the production of 64Cu radionuclide. The electrodeposition experiments were carried out by acid plating baths. Operating parameters such as pH, temperature, and current density are also optimized. The current efficiency was measured at different current densities. The optimum conditions of the zinc electrodeposition were as follows: 6.2 gźl-1 zinc, pH = 3, dc current density of ca. 85.54 mAźcm-2 at 30°C with 98% current efficiency. SEM photomicrographs demonstrated fine-grained structure of the deposit obtained from the optimum bath.