measurement of photo-neutron dose from an 18-mv medical linac using a foil activation method in view of radiation protection of patients
Clicks: 266
ID: 235330
2016
Article Quality & Performance Metrics
Overall Quality
Not rated
Combines reader engagement with the AI quality analysis. This
article has not been analysed, so there is no overall score —
reader engagement is measured and shown alongside.
Reader Engagement
Popular Article
30.0
/100
266 views
33 readers
AI Quality Assessment
Not analyzed
Readership in this journal
PopularRanked #170 of 357 articles by views in Journal of hazardous materials
Most read
Least read
Bar heights use a square-root scale. Only the 120 most-read articles are drawn; the journal has 357 in total.
Mint this article as an NFT
Not yet mintedCreate a permanent, verifiable on-chain record of this article on the Scimatic Network. The NFT is held in your Journament account, and you can withdraw it to your own wallet at any time.
5
SUSD
one-off · no wallet required
Abstract
High-energy linear accelerators are increasingly used in the medical field. However, the unwanted photo-neutrons can also be contributed to the dose delivered to the patients during their treatments. In this study, neutron fluxes were measured in a solid water phantom placed at the isocenter 1-m distance from the head of an 18-MV linac using the foil activation method. The produced activities were measured with a calibrated well-type Ge detector. From the measured fluxes, the total neutron fluence was found to be (1.17 ± 0.06) × 107 n/cm2 per Gy at the phantom surface in a 20 × 20 cm2 X-ray field size. The maximum photo-neutron dose was measured to be 0.67 ± 0.04 mSv/Gy at dmax = 5 cm depth in the phantom at isocenter. The present results are compared with those obtained for different field sizes of 10 × 10cm2, 15 × 15cm2, and 20 × 20cm2 from 10-, 15-, and 18-MV linacs. Additionally, ambient neutron dose equivalents were determined at different locations in the room and they were found to be negligibly low. The results indicate that the photo-neutron dose at the patient position is not a negligible fraction of the therapeutic photon dose. Thus, there is a need for reduction of the contaminated neutron dose by taking some additional measures, for instance, neutron absorbing-protective materials might be used as aprons during the treatment.
| Reference Key |
ycel2016nuclearmeasurement
Use this key to autocite in the manuscript while using
SciMatic Manuscript Manager or Thesis Manager
|
|---|---|
| Authors | ;Haluk Yücel;İbrahim Çobanbaş;Asuman Kolbaşı;Alptuğ Özer Yüksel;Vildan Kaya |
| Journal | Journal of hazardous materials |
| Year | 2016 |
| DOI |
10.1016/j.net.2015.11.003
|
| URL | |
| Keywords |
Citations
No citations found. To add a citation, contact the admin at info@scimatic.org
Comments
No comments yet. Be the first to comment on this article.