Measurement and analysis of neutron and gamma-ray flux spectra in SiC

K. Seidel*, M. Angelone, P. Batistoni, Y. Chen, U. Fischer, H. Freiesleben, C. Negoita, R. L. Perel, M. Pillon, S. Unholzer

*Corresponding author for this work

Research output: Contribution to journalArticlepeer-review

8 Scopus citations


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.

Original languageAmerican English
Pages (from-to)379-383
Number of pages5
JournalFusion Engineering and Design
Issue number1-4 SPEC
StatePublished - Sep 2003

Bibliographical note

Funding Information:
We acknowledge the support by the European Fusion Development Agreement.


  • Gamma-ray
  • Neutron
  • Silicon carbide


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