TITLE

Uranium-233 fission detectors for neutron flux measurement in reactors

AUTHOR(S)
Prasad, K.R.; Balagi, V.
PUB. DATE
June 1996
SOURCE
Review of Scientific Instruments;Jun96, Vol. 67 Issue 6, p2197
SOURCE TYPE
Academic Journal
DOC. TYPE
Article
ABSTRACT
Reports on the development of fission counters using uranium-223 as a sensing material for reactor startup applications. Counting sensitivity of the first model in the pulse mode; Production of highly ionizing fission fragments from neutron interactions with uranium.
ACCESSION #
4295425

 

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