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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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