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 Dosimetryjournal_title
Radiation protection dosimetryauthors
Hajiloo N,Raisali G,Aslani Gdoi
10.1093/rpd/ncn099subject
Has Abstractpub_date
2008-01-01 00:00:00pages
427-33issue
4eissn
0144-8420issn
1742-3406pii
ncn099journal_volume
130pub_type
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