<abstract xmlns="http://www.w3.org/1999/xhtml">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.</abstract>

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.

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

Reactor Research School, Nuclear Science and Technology Research Institute, Tehran,

Nukleonika

This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 3.0 License.

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

The activation method for 99Mo production in comparison to fissionable target irradiation in research reactors is less preferable. Therefore, 99Mo yield using...

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

Published Online: Mar 04, 2017

Page range: 37 - 45

Received: Jan 30, 2016

Accepted: Nov 07, 2016

DOI: https://doi.org/10.1515/nuka-2017-0006

Keywords
research reactor, Mo production, uranyl sulphate, liquid target, MCNPX code

© 2017 Zohreh Gholamzadeh et al., published by De Gruyter Open

This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 3.0 License.

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

Published Online: Mar 04, 2017

Page range: 37 - 45

Received: Jan 30, 2016

Accepted: Nov 07, 2016

DOI: https://doi.org/10.1515/nuka-2017-0006

Keywordsresearch reactor, Mo production, uranyl sulphate, liquid target, MCNPX code

© 2017 Zohreh Gholamzadeh et al., published by De Gruyter Open

This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 3.0 License.

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

Keywords
research reactor, Mo production, uranyl sulphate, liquid target, MCNPX code