Skip Navigation

Radiation Protection Dosimetry 2004 111(1):35-39; doi:10.1093/rpd/nch356
This Article
Right arrow Full Text
Right arrow Full Text (PDF)
Right arrow Alert me when this article is cited
Right arrow Alert me if a correction is posted
Services
Right arrow Email this article to a friend
Right arrow Similar articles in this journal
Right arrow Similar articles in ISI Web of Science
Right arrow Similar articles in PubMed
Right arrow Alert me to new issues of the journal
Right arrow Add to My Personal Archive
Right arrow Download to citation manager
Right arrow Search for citing articles in:
ISI Web of Science (5)
Right arrowRequest Permissions
Google Scholar
Right arrow Articles by Fernandes, A. C.
Right arrow Articles by Osvay, M.
Right arrow Search for Related Content
PubMed
Right arrow PubMed Citation
Right arrow Articles by Fernandes, A. C.
Right arrow Articles by Osvay, M.
Social Bookmarking
Add to CiteULike   Add to Connotea   Add to Del.icio.us  
What's this?

Radiation Protection Dosimetry Vol. 111, No. 1 © Oxford University Press 2004; all rights reserved

Thermoluminescence dosimetry of a thermal neutron field and comparison with Monte Carlo calculations

A. C. Fernandes1,2,*, J. P. Santos1, A. Kling1,2, J. G. Marques1,2, I. C. Gonçalves1, A. Ferro Carvalho1, L. Santos1, J. Cardoso1 and M. Osvay3

1 Instituto Tecnológico e Nuclear, Estrada Nacional 10, P-2686-953 Sacavém, Portugal
2 Centro de Física Nuclear da Universidade de Lisboa, Av. Prof. Gama Pinto, no. 2, P-1649-003 Lisboa, Portugal
3 Institute of Isotope and Surface Chemistry, Budapest P.O. Box 77, H-1525, Hungary

* Corresponding author: anafer{at}itn.mces.pt

The characteristics of thermoluminescence dosemeters (TLDs) regarding the determination of photon and neutron absorbed doses were investigated in a thermal neutron beam. Harshaw TLD-100 (LiF:Mg,Ti) and TLD-700 (7LiF:Mg,Ti) were compared with similar materials from Solid Dosimetric Detector and Method Laboratory (People's Republic of China). Harshaw TLD-700H (7LiF:Mg,Cu,P) and aluminium oxide (Al2O3:Mg,Y) from Hungary were also considered for photon dose measurement. The neutron sensitivity of the investigated materials was measured and found to be consistent with values reported by other authors. A comparison was made between the TL dose measurements and results obtained via conventional methods. An agreement within 20% was obtained, which demonstrates the ability of TLD for measuring neutron and photon doses in a mixed field, using careful calibration procedures and determining the neutron sensitivity for the usage conditions.


Add to CiteULike CiteULike   Add to Connotea Connotea   Add to Del.icio.us Del.icio.us    What's this?


This article has been cited by other articles:


Home page
 Radiat Prot DosimetryHome page
J. P. Santos, A. C. Fernandes, I. C. Goncalves, J. G. Marques, A. F. Carvalho, L. Santos, J. Cardoso, and M. Osvay
Photon and fast neutron dosimetry using aluminium oxide thermoluminescence dosemeters
Radiat Prot Dosimetry, September 1, 2006; 120(1-4): 358 - 360.
[Abstract] [Full Text] [PDF]

Home page
 Radiat Prot DosimetryHome page
A. C. Fernandes, I. C. Goncalves, J. Santos, J. Cardoso, L. Santos, A. Ferro Carvalho, J. G. Marques, A. Kling, A. J. G. Ramalho, and M. Osvay
Dosimetry at the Portuguese research reactor using thermoluminescence measurements and Monte Carlo calculations
Radiat Prot Dosimetry, September 1, 2006; 120(1-4): 349 - 353.
[Abstract] [Full Text] [PDF]


Disclaimer: Please note that abstracts for content published before 1996 were created through digital scanning and may therefore not exactly replicate the text of the original print issues. All efforts have been made to ensure accuracy, but the Publisher will not be held responsible for any remaining inaccuracies. If you require any further clarification, please contact our Customer Services Department.