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 (14)
Right arrowRequest Permissions
Google Scholar
Right arrow Articles by Fiechtner, A.
Right arrow Articles by Wernli, C.
Right arrow Search for Related Content
PubMed
Right arrow Articles by Fiechtner, A.
Right arrow Articles by Wernli, C.
Social Bookmarking
Add to CiteULike   Add to Connotea   Add to Del.icio.us  
What's this?

Radiation Protection Dosimetry 85:35-38 (1999)
© 1999 Oxford University Press

Individual Neutron Monitoring with CR-39 Detectors at an Accelerator Centre

A. Fiechtner and C. Wernli

A new personal neutron dosimetry system at the Paul Scherrer Institute (PSI) is based on chemically etched CR-39 detectors (PN3) with different radiators, and an automatic readout system, the Autoscan 60. The most relevant neutron fields at the PSI accelerator have an energy range up to 600 MeV with peak energies around 1-5 and 50-100 MeV due to evaporation and cascade processes in the concrete shieldings, and partly thermalised spectra that occur at the entrance to the labyrinths. The main radiators used for PN3 are polyethylene (PE) for fast neutrons and PE with lithium for thermal and fast neutrons. For extremely high track densities (corresponding to a dose up to 5 Sv) a transmission spectrometer is used for evaluation, since automatic counting by Autoscan 60 saturates at doses above 100 mSv. The system has been tested for linearity, energy dependence up to 300 MeV neutron energy, angular dependence, and radon background response. It was then calibrated for realistic neutron fields at PSI. The detection limit for these high energy fields is about 0.3 mSv. In addition, calculations have been performed to determine the response of the dosemeter to typical spectra in nuclear power plants.


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
C. Wernli
Individual monitoring at accelerator centres
Radiat Prot Dosimetry, November 1, 2009; 137(1-2): 74 - 82.
[Abstract] [Full Text] [PDF]

Home page
 Radiat Prot DosimetryHome page
R. H. Olsher, T. D. McLean, M. W. Mallett, L. L. Romero, R. T. Devine, and J. M. Hoffman
High-energy response of passive dosemeters in use at LANL
Radiat Prot Dosimetry, August 1, 2007; 126(1-4): 326 - 332.
[Abstract] [Full Text] [PDF]

Home page
 Radiat Prot DosimetryHome page
A. Fiechtner, M. Boschung, and C. Wernli
Performance of a PADC personal neutron dosemeter at simulated and real workplace fields of the nuclear industry
Radiat Prot Dosimetry, August 1, 2007; 126(1-4): 314 - 317.
[Abstract] [Full Text] [PDF]

Home page
 Radiat Prot DosimetryHome page
R. G. Mills, N. M. Spyrou, R. P. Stokes, I. E. Holloway, and P. A. Beeley
Introduction of a thermal response to the DSTL PADC personal neutron dosemeter
Radiat Prot Dosimetry, August 1, 2004; 110(1-4): 309 - 314.
[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.