OPTIMIZATION ANALYSIS OF IRRADIATED TARGETS TRANSPORT SHIELDING TO BE USED IN A 99Mo PRODUCTION PLANT

Year
1992
Author(s)
Adelia Sahyun - Instituto de Pesquisas Energeticas e Nucleares
Gian Maria Sordi - Instituto de Pesquisas Energeticas e Nucleares/ ATOMO Radioproteção e Segurança Nuclear, São Paulo, Brazil
F.L. Biazini Filho - Comissão Nacional de Energia Nuclear. Institute de Pesquisas Energéticas e Nucleares.
C.R. Romero Filho - Comissão Nacional de Energia Nuclear. Institute de Pesquisas Energéticas e Nucleares.
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Abstract
The aim of this paper is to optimize the shielding thickness to transport fission products from IPEN to a laboratory in charge of the separation of 99Mo, which is placed at Great Sao Paulo city (ICRP Publication 55, 1 989). The cooling plus the transport time is 12 hours, according to 99Mo activity of 300 Ci desired after separation. In order to calculate the shielding thickness and doses with different options, codes described elsewhere have been used (ORIGENII:Isotope generation and depletion code-Matrix exponential method, 1 982; ISOSHLD:Kernel integration code purpose isotope shielding analysis, 1 979).