Title of article
Measurement and analysis of neutron and gamma-ray flux spectra in SiC
Author/Authors
Seidel، نويسنده , , K. and Angelone، نويسنده , , M. and Batistoni، نويسنده , , P. and Chen، نويسنده , , Y. and Fischer، نويسنده , , U. and Freiesleben، نويسنده , , H. and Negoita، نويسنده , , C. and Perel، نويسنده , , R.L. and Pillon، نويسنده , , M. and Unholzer، نويسنده , , S.، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2003
Pages
5
From page
379
To page
383
Abstract
A silicon carbide assembly of a thickness corresponding to about 10 mean free path for 14 MeV neutrons was irradiated at the Frascati Neutron Generator and the neutron and gamma-ray flux spectra were measured simultaneously, using a NE 213 scintillation spectrometer at four positions inside the block. The computational analysis of the benchmark experiment for the advanced structural material of fusion devices was performed with the Monte Carlo code MCNP-4C and nuclear data taken from the Fusion Evaluated Nuclear Data Library FENDL/MC-2.0, except for 28Si, for which the new data evaluation of the European Fusion File EFF-3.0 was used. Measured and calculated flux spectra are compared and ratios of calculated-to-experimental values are derived for various energy ranges.
Keywords
Neutron , Gamma-Ray , silicon carbide
Journal title
Fusion Engineering and Design
Serial Year
2003
Journal title
Fusion Engineering and Design
Record number
2351557
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