Prediction of 67Ga production using the Monte Carlo code MCNPX

Author:

Sadeghi M.,Jokar N.,Kakavand T.,Ghafoori Fard H.,Tenreiro C.

Publisher

Elsevier BV

Subject

Radiation

Reference23 articles.

1. A novel technique for simultaneous diagnosis and radioprotection by radioactive cerium oxide nanoparticles: study of cyclotron production of 137mCe;Bakht;J. Radioanal. Nucl. Chem.,2012

2. Briesmeister, J.F. (Ed.), 1997. MCNP-a general Monte Carlo N-particle transport code. Technical Report La-12625-M, Los Alamos.

3. Broeders, C.H.M., Konobeyev, A. Yu, Korovin, A., Lunev, V.P., Blann, M., 2006. ALICE/ASH–Pre-compound and evaporation model code system for calculation of excitation functions, energy and angular distributions of emitted particles in nuclear reactions at intermediate energies, FZK-7183. Available from: 〈http://bibliothek.fzk.de/zb/berichte/FZKA7183.pdf〉.

4. Theoretical cross sections of 209Bi, 232Th, 235U and 238U on deuteron-induced reactions;Büyükuslu;Ann. Nucl. Energy,2010

5. Direct separation of 67Ga citrate from zinc and copper target materials by anion exchange;El-Azony;Appl. Radiat. Isot.,2003

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