Skip Navigation


Radiation Protection Dosimetry Advance Access originally published online on August 1, 2008
Radiation Protection Dosimetry 2008 131(4):418-424; doi:10.1093/rpd/ncn206
This Article
Right arrow Full Text
Right arrow Full Text (PDF)
Right arrow All Versions of this Article:
131/4/418    most recent
ncn206v1
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 Kravchik, T.
Right arrow Articles by Tshuva, A.
Right arrow Search for Related Content
PubMed
Right arrow PubMed Citation
Right arrow Articles by Kravchik, T.
Right arrow Articles by Tshuva, A.
Social Bookmarking
Add to CiteULike   Add to Connotea   Add to Del.icio.us  
What's this?

© The Author 2008. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oxfordjournals.org

Determination of the solubility and size distribution of radioactive aerosols in the uranium processing plant at NRCN

T. Kravchik*, S. Oved, O. Paztal-Levy, O. Pelled, R. Gonen, U. German and A. Tshuva

Nuclear Research Center Negev, POB 9001, Beer-Sheva, Israel

* Corresponding author: tuvkra{at}zahav.net.il

Received May 6, 2008, amended June 26, 2008, accepted July 13, 2008

Inhalation is the main route of internal exposure to radioactive aerosols in the nuclear industry. To assess the radiation dose from the intake of these aerosols, it is necessary to know their physical (aerodynamic diameter distribution) and chemical (dissolution rate in extracellular lung fluid) characteristics. Air samples were taken from the uranium processing plant at the Nuclear Research Center, Negev. Measurements of aerodynamic diameter distribution using a cascade impactor indicated an average activity median aerodynamic diameter value close to 5 µm, in accordance with the recent recommended values of International Commission on Radiological Protection (ICRP) model. Solubility profiles of these aerosols were determined by performing in vitro solubility tests over 100 d in a simultant solution of the extracellular fluid. The tests indicated that the uranium aerosols should be assigned to an absorption between Types M and S (as defined by the ICRP Publication 66 model).


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
T. Kravchik and U. German
A statistical model for reconstruction of historical internal doses for uranium workers
Radiat Prot Dosimetry, September 1, 2009; 136(2): 87 - 94.
[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.