Fast neutron and gamma-ray spectra measurements with a NE-213 spectrometer in the FNG Copper Benchmark Experiment

Klix, A.; Angelone, M.; Fischer, U.; Pillon, M.

doi:10.1016/j.fusengdes.2016.03.007

Cited by 3 publications

(3 citation statements)

References 6 publications

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“…The selected nuclear reactions cover the whole energy range of interest for fusion neutronics, from 14 MeV down to thermal energy. Eight experimental positions were selected inside the Cu block from ∼3.5 cm up to ∼57 cm depth, two of them were also used to measure the neutron spectrum inside the block by mean of NE-213 scintillator [15].…”

Section: Cu Benchmark Experiments and Resultsmentioning

confidence: 99%

“…The MCSEN analysis was devoted to the assessment of sensitivities and uncertainties of the neutron flux at the two positions in the Cu block (25 and 45 cm depth) where the flux spectrum measurements using a NE-213 detector have been performed [15]. The sensitivities of these fluxes in 5 (coarse) energy groups (with upper group energies at 1 keV, 0.1 MeV, 1.0 MeV, 10 MeV and20 MeV) to the cross sections of the two Cu isotopes, 63 Cu and 65 Cu were calculated (Fig.…”

Section: Results With Mcsen5 Codementioning

confidence: 99%

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Copper benchmark experiment for the testing of JEFF-3.2 nuclear data for fusion applications

et al. 2017

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A neutronics benchmark experiment on a pure Copper block (dimensions 60 × 70 × 70 cm 3) aimed at testing and validating the recent nuclear data libraries for fusion applications was performed in the frame of the European Fusion Program at the 14 MeV ENEA Frascati Neutron Generator (FNG). Reaction rates, neutron flux spectra and doses were measured using different experimental techniques (e.g. activation foils techniques, NE213 scintillator and thermoluminescent detectors). This paper first summarizes the analyses of the experiment carried-out using the MCNP5 Monte Carlo code and the European JEFF-3.2 library. Large discrepancies between calculation (C) and experiment (E) were found for the reaction rates both in the high and low neutron energy range. The analysis was complemented by sensitivity/uncertainty analyses (S/U) using the deterministic and Monte Carlo SUSD3D and MCSEN codes, respectively. The S/U analyses enabled to identify the cross sections and energy ranges which are mostly affecting the calculated responses. The largest discrepancy among the C/E values was observed for the thermal (capture) reactions indicating severe deficiencies in the 63,65 Cu capture and elastic cross sections at lower rather than at high energy. Deterministic and MC codes produced similar results. The 14 MeV copper experiment and its analysis thus calls for a revision of the JEFF-3.2 copper cross section and covariance data evaluation. A new analysis of the experiment was performed with the MCNP5 code using the revised JEFF-3.3-T2 library released by NEA and a new, not yet distributed, revised JEFF-3.2 Cu evaluation produced by KIT. A noticeable improvement of the C/E results was obtained with both new libraries.

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Section: Cu Benchmark Experiments and Resultsmentioning

confidence: 99%

Section: Results With Mcsen5 Codementioning

confidence: 99%

Copper benchmark experiment for the testing of JEFF-3.2 nuclear data for fusion applications

et al. 2017

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“…In the last two decades, the search for high performance scintillators has led to the discovery of new scintillating materials [3,4], some of which are sensitive to both neutrons and gamma-rays. Examples are Elpasolite scintillators [5][6][7][8][9][10], lithium based glass scintillators [11][12][13][14][15][16], some classes of liquid scintillators [11,[17][18][19] and plastic scintillators [20,21]. An interesting example from the Elpasolite family is the Cs2LiYCl6:Ce (CLYC) scintillator, considered to be one of the most promising inorganic scintillators with an excellent energy resolution of less than 5% at 662 keV [4,22].…”

Section: Introductionmentioning

confidence: 99%

Material optimization in dual particle detectors by comparing advanced scintillating materials using two Monte Carlo codes

Hamrashdi¹,

Cheneler²,

Monk³

2017

Nuclear Instruments and Methods in Physics Research Section A:

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A new generation of scintillating materials have been recently developed in the radiation-imaging field offering very promising dual particle detection abilities. Here, four different scintillating materials (Cs2LiYCl6:Ce (CLYC), 95% 6 Li enriched Cs2LiYCl6:Ce (CLYC-6), natural Li-glass scintillator (GS10) and liquid scintillator EJ-309) have been characterized for their abilities to attenuate thermal neutrons, fast neutrons and gamma-rays. Recent studies regarding these materials overlook these fundamental characteristics, which can directly affect the design process of advanced imaging systems such as Compton cameras and dual particle imaging systems. The response of each featured material to these three types of radiation fields was simulated with two different Monte Carlo codes, MCNP6 and Geant4. The results indicated that among these four materials, natural Li-glass scintillator (GS10) has the highest thermal neutron detection efficiency and the highest elastic scattering efficiencies. However, the attenuation of fast neutrons was found to be the most severe in EJ-309 liquid scintillator. When gamma-rays are considered, it was found that the mass attenuation coefficient of CLYC and CLYC-6 is the highest of the four materials considered when energies lower than 1 MeV are incident. It is intended that this work will lead to the design and the build of an advanced prototype three stage Compton Camera which will be sensitive to both neutrons and Gamma rays.

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Fast neutron spectra measurement in a copper using a 252Cf standard neutron source

Schulc

Košťál

Matěj

et al. 2022

Radiation Physics and Chemistry

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Fast neutron and gamma-ray spectra measurements with a NE-213 spectrometer in the FNG Copper Benchmark Experiment

Cited by 3 publications

References 6 publications

Copper benchmark experiment for the testing of JEFF-3.2 nuclear data for fusion applications

Copper benchmark experiment for the testing of JEFF-3.2 nuclear data for fusion applications

Material optimization in dual particle detectors by comparing advanced scintillating materials using two Monte Carlo codes

Fast neutron spectra measurement in a copper using a 252Cf standard neutron source

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