Reactor Neutron Measurements with Fission Foil-Lexan Detectors
作者:
RagoP. F.,
GoldsteinN.,
TochilinE.,
期刊:
Nuclear Applications and Technology
(Taylor Available online 1970)
卷期:
Volume 8,
issue 3
页码: 302-309
ISSN:0550-3043
年代: 1970
DOI:10.13182/NT70-A28678
出版商: Taylor&Francis
数据来源: Taylor
摘要:
A fissian foil-Lexan detector system has been developed to monitor reactor neutrons. It is similar to the system based on counting fission gamma rays but has some advantages; i.e., permanently recorded tracks that can be read any time after exposure; integrated recording; microgram amounts of fissionable material needed; and the elimination of specialized gamma-ray counting equipment. Fission-product damage tracks in the Lexan (or mica) are counted under an optical microscope. For thick foils, fluence is determined from the sensitivity factor of 1.16×10−5tracks/(neutron-barn).Fluence measurements with the two systems are compared for several reactor environments while dose measurements are compared with tissue-equivalent calorimeter values. The use of232Th to replace238U as the fissionable isotope for the energy interval of 1.5 to 3 MeV, and of235U to replace239Pu for energies3 MeV.
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