Skip Navigation



Radiation Protection Dosimetry Advance Access published online on March 23, 2005
Radiation Protection Dosimetry, doi:10.1093/rpd/nch477
This Article
Right arrow Full Text (PDF)
Right arrow All Versions of this Article:
113/4/442    most recent
nch477v1
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 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 arrowRequest Permissions
Google Scholar
Right arrow Articles by Veinot, K. G.
Right arrow Articles by Hertel, N. E.
Right arrow Search for Related Content
PubMed
Right arrow PubMed Citation
Right arrow Articles by Veinot, K. G.
Right arrow Articles by Hertel, N. E.
Social Bookmarking
Add to CiteULike   Add to Connotea   Add to Del.icio.us  
What's this?

© The Author 2005. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oupjournals.org
Received August 6, 2004
Revised February 14, 2005
Accepted February 22, 2005

SCIENTIFIC AND TECHNICAL PAPER

RESPONSE OF HARSHAW NEUTRON THERMOLUMINESCENCE DOSEMETERS IN TERMS OF THE REVISED ICRP/ICRU RECOMMENDATIONS

K. G. Veinot 1* and N. E. Hertel 2

1 Y-12 National Security Complex, P.O. Box 2009, M.S. 8105, Oak Ridge, TN 37831-8105, USA
2 George W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, Atlanta, GA 30332-0405, USA

* To whom correspondence should be addressed.
K. G. Veinot, E-mail: veinotkg{at}y12.doe.gov


  Abstract

To monitor workers for external neutron radiation dose, the Y-12 National Security Complex utilises the thermoluminescence dosemeters (TLDs) manufactured by Harshaw. At Y-12, the majority of external dose to workers is due to low-energy photon and/or beta particles emitted from uranium and its progeny. However, some neutron dose is expected since neutrons are produced from ({alpha},n) reactions in various compounds found at the plant, including UF4 and UF6. Neutron sources, such as 252Cf, are also used throughout the complex. The Harshaw neutron dosemeter consists of two gamma-sensitive elements (7Li) and two neutron-sensitive elements enriched in 6Li with various shielding/filter materials placed around each of them. In this work, the energy response of the dosemeter to neutrons has been calculated using the Monte Carlo transport code MCNP Version 4-C and, these results are compared with the measured response of the dosemeter to unmoderated and D2O- moderated 252Cf neutrons. The response of the dosemeter has also been determined in terms of the personal absorbed dose and personal dose equivalent as a function of neutron energy based on the recommendations of the ICRP Publication 60 and ICRU Report 49. The energy response of the dosemeter characteristics can be used to generate spectral conversion coefficients for routine neutron absorbed dose and dose equivalent calculations.


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




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.