Measurement of a fast neutron leakage spectrum from graphite cylinder driven by D-T generator

Abstract This paper deal with leakage measurements performed on a fusion DT generator using a graphite target. The main objective was to verify or refute the observed discrepancy between calculations and experiments at higher neutron energies. The measurements were performed using a well validated stilbene scintillation detector. The obtained spectrum was then compared with Monte Carlo calculations using the MCNP code and various nuclear data libraries. The results show a persistent discrepancy between the experiment and the calculations, regardless of the neutron source used and the concept of the experiment itself, especially in the energy range of 6.5–8.5 MeV and in energies above 11 MeV. The measurements thus serve as supplementary data to the reactor experiments carried out and point to the need for further refinement of the nuclear data of graphite in the fast neutron range.

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Publication Details

Journal
Journal of Nuclear Engineering and Radiation Science
Published
2026-07-28
DOI
https://doi.org/10.1115/1.4072404
Primary Topic
Graphite, nuclear technology, radiation studies
Type
article
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article

Measurement of a fast neutron leakage spectrum from graphite cylinder driven by D-T generator

Evžen Novák, Tomáš Peltan, Marek Zmeškal, Tomáš Czakoj et al.
Journal of Nuclear Engineering and Radiation Science
Graphite, nuclear technology, radiation studies
article

Measurement of a fast neutron leakage spectrum from graphite cylinder driven by D-T generator

Evžen Novák, Tomáš Peltan, Marek Zmeškal, Tomáš Czakoj, Michal Košťál
article en

Abstract

Abstract This paper deal with leakage measurements performed on a fusion DT generator using a graphite target. The main objective was to verify or refute the observed discrepancy between calculations and experiments at higher neutron energies. The measurements were performed using a well validated stilbene scintillation detector. The obtained spectrum was then compared with Monte Carlo calculations using the MCNP code and various nuclear data libraries. The results show a persistent discrepancy between the experiment and the calculations, regardless of the neutron source used and the concept of the experiment itself, especially in the energy range of 6.5–8.5 MeV and in energies above 11 MeV. The measurements thus serve as supplementary data to the reactor experiments carried out and point to the need for further refinement of the nuclear data of graphite in the fast neutron range.

Journal of Nuclear Engineering and Radiation Science
Research Centre Rez (CZ), University of West Bohemia in Pilsen (CZ)
Affordable and clean energy
Openalex Percentile: Top 19%
Graphite, nuclear technology, radiation studies
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