DocumentCode
863625
Title
A Portable Neutron Spectrometer/Dosimeter
Author
Waechter, D.A. ; Erkkila, B.H. ; Vasilik, D.G.
Author_Institution
Health Division Los Alamos National Laboratory Los Alamos, New Mexico, 87545
Volume
30
Issue
1
fYear
1983
Firstpage
525
Lastpage
527
Abstract
As part of the continuing DOE effort to upgrade personnel neutron dosimetry, the Health Division at Los Alamos has developed a portable, battery-operated, computerized neutron spectrometer/dosimeter. The instrument has a built-in tissue-equivalent LET neutron detector, 128-channel pulse height analyzer with integral liquid crystal display, and a microcomputer system which calculates dose and dose rate from neutrons incident on the detector. The instrument will, at the user´s option, display a raw data spectrum or a spectrum of rad or rem as a function of keV per micron of equivalent tissue. The dosimeter will also calculate and display accumulated dose in millirad and millirem, as well as giving the user neutron dose rates in millirad and millirem per hour.
Keywords
Detectors; Dosimetry; Instruments; Liquid crystal displays; Microcomputers; Neutrons; Personnel; Portable computers; Spectroscopy; US Department of Energy;
fLanguage
English
Journal_Title
Nuclear Science, IEEE Transactions on
Publisher
ieee
ISSN
0018-9499
Type
jour
DOI
10.1109/TNS.1983.4332324
Filename
4332324
Link To Document