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

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

Identyfikatory

DOI

10.1515/nuka-2017-0006

• Języki publikacji: EN

Abstrakty

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.

Słowa kluczowe

EN

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

• Wydawca: Institute of Nuclear Chemistry and Technology
• Czasopismo: Nukleonika
• Rocznik: 2017
• Tom: Vol. 62, No. 1
• Strony: 37--45
• Opis fizyczny: Bibliogr. 29 poz., rys.

Twórcy

autor

Gholamzadeh Z.

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

autor

Mirvakili S. M.

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

autor

Davari A.

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

autor

Alizadeh M.

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

autor

Joz-Vaziri A.

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

Bibliografia

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Uwagi

PL

Opracowanie ze środków MNiSW w ramach umowy 812/P-DUN/2016 na działalność upowszechniającą naukę (zadania 2017).