Analysis and improvement of cyclotron thallium target room shield.

Abstract:

:Because of high neutron and gamma-ray intensities generated during bombardment of a thallium-203 target, a thallium target-room shield and different ways of improving it have been investigated. Leakage of neutron and gamma ray dose rates at various points behind the shield are calculated by simulating the transport of neutrons and photons using the Monte Carlo N Particle transport computer code. By considering target-room geometry, its associated shield and neutron and gamma ray source strengths and spectra, three designs for enhancing shield performance have been analysed: a shielding door at the maze entrance, covering maze walls with layers of some effective materials and adding a shadow-shield in the target room in front of the radiation source. Dose calculations were carried out separately for different materials and dimensions for all the shielding scenarios considered. The shadow-shield has been demonstrated to be one suitable for neutron and gamma dose equivalent reduction. A 7.5-cm thick polyethylene shadow-shield reduces both dose equivalent rate at maze entrance door and leakage from the shield by a factor of 3.

journal_name

Radiat Prot Dosimetry

authors

Hajiloo N,Raisali G,Aslani G

doi

10.1093/rpd/ncn099

subject

Has Abstract

pub_date

2008-01-01 00:00:00

pages

427-33

issue

4

eissn

0144-8420

issn

1742-3406

pii

ncn099

journal_volume

130

pub_type

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