Atieh Jozvaziri scite author profile

The activation method for 99Mo production in comparison to fissionable 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.

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Investigation of safety aspects during steady state operation of Tehran research reactor fuel test loop

Arshi

Mozafari

Jozvaziri

et al. 2021

Progress in Nuclear Energy

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A methodology to enhance thermal neutron flux in Tehran Research Reactor core for domestic fuel test purposes

Arshi

Jozvaziri

Mirvakili

et al. 2021

Progress in Nuclear Energy

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Computational simulation of nat UO 2 , 232 ThO 2 and U 3 O 8 -Al pills to estimate (p,fission) 99 Mo yield in the modeled targets irradiated by CYCLONE30 accelerator

Jozvaziri

Gholamzadeh

Yousefi

et al. 2017

Applied Radiation and Isotopes

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Atieh Jozvaziri

Modeling of neutron diffractometry facility of Tehran Research Reactor using Vitess 3.3a and MCNPX codes

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

Investigation of safety aspects during steady state operation of Tehran research reactor fuel test loop

A methodology to enhance thermal neutron flux in Tehran Research Reactor core for domestic fuel test purposes

Computational simulation of nat UO 2 , 232 ThO 2 and U 3 O 8 -Al pills to estimate (p,fission) 99 Mo yield in the modeled targets irradiated by CYCLONE30 accelerator

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Atieh Jozvaziri

Modeling of neutron diffractometry facility of Tehran Research Reactor using Vitess 3.3a and MCNPX codes

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

Investigation of safety aspects during steady state operation of Tehran research reactor fuel test loop

A methodology to enhance thermal neutron flux in Tehran Research Reactor core for domestic fuel test purposes

Computational simulation of nat UO 2 , 232 ThO 2 and U 3 O 8 -Al pills to estimate (p,fission) 99 Mo yield in the modeled targets irradiated by CYCLONE30 accelerator

Contact Info

Product

Resources

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