Characterization of the neutron spectra in three irradiation channels of the JSI TRIGA reactor using the GRUPINT spectrum adjustment code

Radulović, Vladimir; Jačimović, Radojko; Pungerčič, Anže; Vavtar, Ingrid; Snoj, Luka; Trkov, A.

doi:10.1016/j.nds.2020.07.003

Cited by 15 publications

(4 citation statements)

References 25 publications

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“…The neutron energy spectrum and irradiation settings are the same as in the previously reported study [43]. Figure 1 displays the neutron spectra in the pneumatic tube (PT) irradiation channel, located in the F-24 core position, obtained by Monte Carlo simulation using the MCNP code [44] and subsequently characterized on the basis of experimental neutron activation measurements [45]. Elastic collisions of incident neutrons with atoms of SiC crystal result in the introduction of intrinsic defects.…”

Section: Methodsmentioning

confidence: 99%

Depth Profile Analysis of Deep Level Defects in 4H-SiC Introduced by Radiation

et al. 2020

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Deep level defects created by implantation of light-helium and medium heavy carbon ions in the single ion regime and neutron irradiation in n-type 4H-SiC are characterized by the DLTS technique. Two deep levels with energies 0.4 eV (EH1) and 0.7 eV (EH3) below the conduction band minimum are created in either ion implanted and neutron irradiated material beside carbon vacancies (Z1/2). In our study, we analyze components of EH1 and EH3 deep levels based on their concentration depth profiles, in addition to (−3/=) and (=/−) transition levels of silicon vacancy. A higher EH3 deep level concentration compared to the EH1 deep level concentration and a slight shift of the EH3 concentration depth profile to larger depths indicate that an additional deep level contributes to the DLTS signal of the EH3 deep level, most probably the defect complex involving interstitials. We report on the introduction of metastable M-center by light/medium heavy ion implantation and neutron irradiation, previously reported in cases of proton and electron irradiation. Contribution of M-center to the EH1 concentration profile is presented.

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Section: Methodsmentioning

confidence: 99%

Depth Profile Analysis of Deep Level Defects in 4H-SiC Introduced by Radiation

et al. 2020

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“…From the measurements we computed bare vs. filtered reaction rate ratios. Reaction rate ratios for the measured nuclear reactions were calculated using the GRUPINT code 4 . The ratios were computed using the neutron spectrum in the PT irradiation channel, previously characterized using the GRUPINT code on the basis of Monte Carlo calculations and measured reaction rate ratios 4 .…”

Section: Boron Based Neutron Filtersmentioning

confidence: 99%

“…The ability to accurately measure neutrons in the fast and epithermal range is therefore of significant importance in future advanced fission and fusion reactors, in particular to monitor the reactor power level, achieved by on-line nuclear instrumentation, and to assess neutron fluence levels in critical reactor components, giving rise to radiation induced effects in materials and systems. Figure 1 displays neutron spectra in different nuclear environments obtained by Monte Carlo simulations: the XAMR® molten salt fast neutron microreactor designed to utilize spent nuclear fuel, as a representative of fast fission systems (courtesy of the NAAREA SAS company), the ITER tokamak 2 as a representative of fusion reactors, the Krško Nuclear Power Plant (NPP) 3 and the Jožef Stefan Institute (JSI) TRIGA research reactor 4 as representatives of thermal fission systems. The thermal, epithermal and fast energy ranges are highlighted.…”

Section: Introductionmentioning

confidence: 99%

Epithermal neutron activation dosimetry - (n,γ) reactions under boron-based filters

Radulović,

Thiollay,

Carcreff

et al. 2024

Preprint

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Neutron activation dosimetry is the primary method for the determination of the neutron flux or fluence, and in general, it is sensitive to the thermal and resonance energy ranges (radiative capture reactions - (n,g) reactions) and the fast energy range (threshold reactions). However, there are very few nuclear reactions which are sensitive specifically to neutrons in the intermediate - epithermal - energy region. This energy region, along with the fast energy range, will become particularly important in the development and deployment of new reactor technologies (Generation IV reactors and Small Modular Reactors - SMRs), which are currently being championed as technologies enabling a meaningful contribution to decarbonization and the fight against climate change, as well as nuclear fusion. The epithermal neutron energy range is also of particular importance for Boron Neutron Capture Therapy (BNCT), a neutron-based cancer therapy, particularly effective for the treatment of head and neck cancer, malignant meningioma, melanoma and hepatocellular carcinoma. This work investigates and demonstrates the applicability of a particular set of (n,g) reactions in conjunction with boron-based neutron filters to achieve sensitivity in the epithermal energy region, and discusses avenues for future research in this context.

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“…The TRIGA reactor fuel consists of a uniform mixture of uranium (8.5 %wt, enriched to 19.7% of 235 U) and zirconium hydride and it is contained in stainless steel cylindrical elements of approximately 73.2 cm in length and 3.6 cm in diameter. Similar to many other research reactors, the CNESTEN's TRIGA is designed to effectively implement a wide range of applications, including the production of radioisotopes for medical and industrial purposes [1] [2], qualification, under irradiation, fuel materials, inert materials and sensors [3] [4] [5] [6], validation and qualification of modelling and simulation tools [7] [8] [9] [10] [11] [12]. The implementation of such applications requires a reliable characterization of the neutron and photon fluxes in the reactor core.…”

Section: Introductionmentioning

confidence: 99%

Absolute neutron and photon flux characterization in the CNESTEN’s TRIGA Mark II research reactor

Ghninou,

Gruel,

Lyoussi

et al. 2023

EPJ Web Conf.

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The National Center for Nuclear Energy, Sciences and Technology (CNESTEN) located in Rabat, Morocco, operates a 2 MW TRIGA Mark II research reactor. This type of reactor is specially designed to effectively implement the various fields of nuclear research such as neutron activation analysis, neutron radiography, detectors testing, radioisotopes production as well as education and training. In the last few years, a collaboration between the French Atomic Energy and Alternative Energies Commission (CEA) and the CNESTEN was established to expand the utilization of the TRIGA computational model by carrying out new in-situ measurements in order to characterize neutron and photon fields within and beyond the TRIGA reactor core. These new measurements will consolidate the knowledge of neutron and photon fluxes in different irradiation and instrumentation channels. The results of these experiments will also be used to extend the experimental validation of the new developed TRIPOLI-4® computational model of the reactor and to quantify the uncertainties and biases. This paper focuses on the neutron and photon flux characterization of two irradiation channels inside the TRIGA reactor core. Neutron measurements are ensured by activation dosimetry whereas photon measurements are ensured by thermo-luminescent detectors (TLD400 – CaF2: Mn). Based on these techniques, the experiments were carried out during an experimental campaign conducted in June 2022. Preceding the implementation of these measurements, two experimental devices were specifically designed and manufactured to ensure a reproducible positioning of the detectors in the selected irradiation channels. This paper presents the experimental results analysis and the associated uncertainty quantification. These results will be then compared to the calculation ones obtained by the computational models of the TRIGA reactor.

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Characterization of the neutron spectra in three irradiation channels of the JSI TRIGA reactor using the GRUPINT spectrum adjustment code

Cited by 15 publications

References 25 publications

Depth Profile Analysis of Deep Level Defects in 4H-SiC Introduced by Radiation

Depth Profile Analysis of Deep Level Defects in 4H-SiC Introduced by Radiation

Epithermal neutron activation dosimetry - (n,γ) reactions under boron-based filters

Absolute neutron and photon flux characterization in the CNESTEN’s TRIGA Mark II research reactor

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