-
Views
-
Cite
Cite
M. Luszik-Bhadra, W.G. Alberts, E. Piesch, Neutron Energy Response and Background of Electrochemically Etched Nuclear Track Detectors: Study of Various CR-39 Materials, Radiation Protection Dosimetry, Volume 32, Issue 2, 1 August 1990, Pages 99–103, https://doi.org/10.1093/oxfordjournals.rpd.a080723
- Share Icon Share
Abstract
The dose equivalent response was investigated for etched track detectors using various CR-39 materials with monoenergetic neutrons between 70 keV and 14.8 MeV and a 252Cf neutron source. A two-step electrochemical etching procedure was employed for all experiments. Results are presented for the energy dependence of the response of the various materials as well as for track background and track diameter distributions.
This content is only available as a PDF.
Radiation Protection Dosimetry
Issue Section:
Article
You do not currently have access to this article.