Possibility of Obtaining High-Activity 177Lu in the IR-8 Research Reactor


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Аннотация

The results of the production of the medical isotope 177Lu in the IR-8 research reactor are presented. The quantitative and qualitative characteristics of the desired radionuclide are determined. The radiochemical method of separating 177Lu from an irradiated target 176Yb by a combination of two electrochemical processes – cementation of ytterbium from acetate-chloride solution on sodium amalgam and electrolysis of an ytterbium solution in a single electrolytic cell – is proposed. The purification factor for removal of 176Yb from 177Lu was 105–106.

Авторлар туралы

P. Boldyrev

National Research Center Kurchatov Institute

Email: j-atomicenergy@yandex.ru
Ресей, Moscow

V. Zagryadskii

National Research Center Kurchatov Institute

Email: j-atomicenergy@yandex.ru
Ресей, Moscow

D. Erak

National Research Center Kurchatov Institute

Email: j-atomicenergy@yandex.ru
Ресей, Moscow

A. Kurochkin

National Research Center Kurchatov Institute

Email: j-atomicenergy@yandex.ru
Ресей, Moscow

D. Markovskii

National Research Center Kurchatov Institute

Email: j-atomicenergy@yandex.ru
Ресей, Moscow

O. Mikhin

National Research Center Kurchatov Institute

Email: j-atomicenergy@yandex.ru
Ресей, Moscow

M. Proshin

National Research Center Kurchatov Institute

Email: j-atomicenergy@yandex.ru
Ресей, Moscow

N. Khmyzov

National Research Center Kurchatov Institute

Email: j-atomicenergy@yandex.ru
Ресей, Moscow

D. Chuvilin

National Research Center Kurchatov Institute

Email: j-atomicenergy@yandex.ru
Ресей, Moscow

Yu. Yashin

National Research Center Kurchatov Institute

Email: j-atomicenergy@yandex.ru
Ресей, Moscow

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