DocumentCode
790003
Title
The use of a Gamma Sensitive Detector to Measure Thermal Reactor Power
Author
Czaika, J. ; Kerr, W.
Author_Institution
Department of Nuclear Engineering the University of Michigan Ann Arbor, Michigan 48105
Volume
16
Issue
1
fYear
1969
Firstpage
255
Lastpage
259
Abstract
A study was made of the feasibility of measuring power output of a thermal reactor with a gamma sensitive detector. Shielding was used to selectively attenuate gammas from fission products as compared to(n,r) reactions and prompt fission gammas. Measurements indicate agreement between detector response and reactor power output, determined independently, over more than three decades. There is evidence that effects of local neutron flux perturbations, seen by neutron chambers, are ignored by the gamma detector.
Keywords
Delay; Electromagnetic wave absorption; Fission reactors; Gamma ray detection; Gamma ray detectors; Gamma rays; Inductors; Neutrons; Nuclear measurements; Power measurement;
fLanguage
English
Journal_Title
Nuclear Science, IEEE Transactions on
Publisher
ieee
ISSN
0018-9499
Type
jour
DOI
10.1109/TNS.1969.4325115
Filename
4325115
Link To Document