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Optimal shielding design for bunkers of compact cyclotrons used in the production of medical radionuclides
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10.1118/1.3515458
/content/aapm/journal/medphys/37/12/10.1118/1.3515458
http://aip.metastore.ingenta.com/content/aapm/journal/medphys/37/12/10.1118/1.3515458

Figures

Image of FIG. 1.
FIG. 1.

Some typical layouts for pet cyclotrons bunkers, designated in this work as (a) direct-shielded door, (b) simple maze, (c) intermediary maze, and (d) double-legged maze.

Image of FIG. 2.
FIG. 2.

Percent transmission versus thickness of ordinary concrete for the neutron source term studied in this work.

Image of FIG. 3.
FIG. 3.

Neutron ambient dose equivalent reduction as a function of maze length.

Image of FIG. 4.
FIG. 4.

Neutron spectra at 1 m from the source, inside a standard cyclotron bunker.

Image of FIG. 5.
FIG. 5.

Mesh tally depiction of neutron ambient dose equivalents (Sv/h) inside a cyclotron vault, considering (a) the existence of a 5 cm thick borated polyethylene door in the inner maze entrance or (b) the absence of the borated polyethylene door.

Tables

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TABLE I.

Most used positron emitters and reactions employed for their production (Ref. 1).

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TABLE II.

Neutron source term used in the simulations.

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TABLE III.

Chemical composition of shielding materials considered in the simulations (relative weight contribution) (Ref. 14).

Generic image for table
TABLE IV.

Neutron and photon ambient dose equivalents rates and average neutron energies at the entrance of the vaults studied in this work for of integrated proton current hitting the target.

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/content/aapm/journal/medphys/37/12/10.1118/1.3515458
2010-11-19
2014-04-19
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752b84549af89a08dbdd7fdb8b9568b5 journal.articlezxybnytfddd
Scitation: Optimal shielding design for bunkers of compact cyclotrons used in the production of medical radionuclides
http://aip.metastore.ingenta.com/content/aapm/journal/medphys/37/12/10.1118/1.3515458
10.1118/1.3515458
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