Skip Navigation


Radiation Protection Dosimetry Advance Access originally published online on August 4, 2008
Radiation Protection Dosimetry 2008 131(4):455-468; doi:10.1093/rpd/ncn204
This Article
Right arrow Full Text
Right arrow Full Text (PDF)
Right arrow All Versions of this Article:
131/4/455    most recent
ncn204v1
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 arrowRequest Permissions
Google Scholar
Right arrow Articles by Smetanin, M.
Right arrow Articles by Potiriadis, C.
Right arrow Search for Related Content
PubMed
Right arrow PubMed Citation
Right arrow Articles by Smetanin, M.
Right arrow Articles by Potiriadis, C.
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

Measurements and Monte Carlo calculations of photon energy distributions in MAYAK PA workplaces

M. Smetanin1, E. Vasilenko1, M. Semenov1, S. Xanthos2, G. Takoudis2, A. Clouvas2,*, J. Silva2,3 and C. Potiriadis2,4

1 MAYAK PA, Lenin street 31, 456780 Ozyorsk, Russia
2 Department of Electrical and Computer Engineering, Aristotle University of Thessaloniki, GR-54124 Thessaloniki, Greece
3 Universite Pierre et Marie Curie (Paris VI), U.F.R. Physique BC212, 4 Place Jussieu, 7525 Paris cedex 05, France
4 Greek Atomic Energy Commission, GR-15310 AgiaParaskevi, Athens, Greece

* Corresponding author: clouvas{at}eng.auth.gr

Received March 31, 2008, amended July 1, 2008, accepted July 13, 2008

Photon energy distributions were measured in different workplaces of the Mayak Production Association (MPA), which was the first plutonium production plant in the former Soviet Union. In situ gamma spectrometry measurements were performed with a portable germanium detector. The spectral stripping method is used for the conversion of the in situ gamma-ray spectra to photon fluence rate energy distribution. This method requires the simulation of the portable germanium detector, which has been performed based on the MCNP code of Los Alamos. Measured photon fluence rate energy distributions were compared with calculated photon energy distributions (with the MCNP code) in two different workplaces: in the first workplace the geometry exposure was known. On the contrary, in the second workplace, as in most workplaces of MPA, the exposure geometry was unknown. The results obtained from the comparison between the experimental and calculated photon fluence rate energy distributions are presented and discussed.


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.