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

Nukleonika

Davari Amin¹  Alizadeh Mosoumeh¹  Gholamzadeh Zohreh¹  Joz-Vaziri Atieh¹  Mirvakili Seyed Mohammad¹ 

[1] Reactor Research School, Nuclear Science and Technology Research Institute, Tehran, Iran (Islamic Republic of);

关键词: research reactor;    99Mo production;    uranyl sulphate;    liquid target;    MCNPX code;   

DOI  :  10.1515/nuka-2017-0006

来源: DOAJ

【 摘 要 】

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.

【 授权许可】

Unknown