Skip Navigation

This Article
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 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 (2)
Right arrowRequest Permissions
Google Scholar
Right arrow Articles by Drake, P.
Right arrow Articles by Solstrand, C.
Right arrow Search for Related Content
PubMed
Right arrow Articles by Drake, P.
Right arrow Articles by Solstrand, C.
Social Bookmarking
Add to CiteULike   Add to Connotea   Add to Del.icio.us  
What's this?

Radiation Protection Dosimetry 80:411-416 (1998)
© 1998 Oxford University Press

Measurement of Neutron Dose Equivalent Close to a Supposedly Stuck Transport Cask with Spent Reactor Fuel

P. Drake, L. Lindborg and C. Solstrand

The individual doses received during normal handling of spent fuel in transport casks are at or below 3 mSv per annum. At these low exposure levels it is sufficient to ascertain that the individual dosemeters show conservative values and to complement this with monitoring of the workplace. If a transport cask with spent fuel must be maintained without water shielding for long periods of time it becomes necessary to reduce the degree of conservatism offered by the dosemeters in normal use. Estimations of the personal dose equivalent at a few positions close to a transport cask are described. The estimation is based on measured neutron energy and angular distributions and on algorithms for combining the reading of two dosemeters. The new (ICRP 60) Q(L) function and new stopping powers (ICRU 49) are used. For the tested irradiation conditions (calculated as well as measured) the personal dose equivalent gives a slightly conservative estimate of E (100% to 140%). To reach this agreement only one dosemeter is needed for irradiation towards the anterior, right or left sides of the body while for irradiation towards the posterior side of the body two dosemeters (front and back) are needed.


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.