Development of neutron spectrum analysis method to assess the content of fissile isotopes in SFA

UDC: 
УДК 53.082.79

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Abstract: 

The paper presents the integrated neutron spectrum analysis as a potential
method for estimating the contents of fissile isotopes in SFAs. Two method
implementation variants are described: (1) measurement of SFA average
transmission and (2) measurement of sample average transmission in the spectrum
that has passed a SFA. The authors describe the dependences of SFA average
transmission on its content of the required isotope obtained by means of two types
of detectors: helium counter tube and fission chamber. Also, the authors propose a
method to estimate SFA burnup by means of the integrated NSA. In addition, SFA
residence time influence on transmission is estimated.

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