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

doi:10.1016/S0920-3796(03)00077-2

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

Racah Institute of Physics

Research output: Contribution to journal › Article › peer-review

8 Scopus citations

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.

Original language	English
Pages (from-to)	379-383
Number of pages	5
Journal	Fusion Engineering and Design
Volume	69
Issue number	1-4 SPEC
DOIs	https://doi.org/10.1016/S0920-3796(03)00077-2
State	Published - Sep 2003

Bibliographical note

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

Keywords

Gamma-ray
Neutron
Silicon carbide

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

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10.1016/S0920-3796(03)00077-2

Cite this

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title = "Measurement and analysis of neutron and gamma-ray flux spectra in SiC",

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 = "Gamma-ray, Neutron, Silicon carbide",

author = "K. Seidel and M. Angelone and P. Batistoni and Y. Chen and U. Fischer and H. Freiesleben and C. Negoita and Perel, {R. L.} and M. Pillon and S. Unholzer",

note = "Funding Information: We acknowledge the support by the European Fusion Development Agreement.",

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doi = "10.1016/S0920-3796(03)00077-2",

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AU - Seidel, K.

AU - Angelone, M.

AU - Batistoni, P.

AU - Chen, Y.

AU - Fischer, U.

AU - Freiesleben, H.

AU - Negoita, C.

AU - Perel, R. L.

AU - Pillon, M.

AU - Unholzer, S.

N1 - Funding Information: We acknowledge the support by the European Fusion Development Agreement.

PY - 2003/9

Y1 - 2003/9

N2 - 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.

AB - 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.

KW - Gamma-ray

KW - Neutron

KW - Silicon carbide

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

Abstract

Bibliographical note

Keywords

UN SDGs

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