Thermal neutron flux
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In this paper, a thermal neutron beam for neutron capture studies at the horizontal neutron channel No.2 of the Dalat Nuclear Research Reactor (DNRR) is designed and simulated using the MCNP5 code.
9p vispiderman 15-06-2023 2 2 Download
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The obtained results with the neutron flux correction were found to be in good agreement with the certified values. In conclusion, the proposed technique can be applied for activation analyses without sandwiching flux monitors between samples during irradiations.
10p vicedric 08-02-2023 4 3 Download
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A new PGNAA facility has been installed at horizontal channel No.4 of the Dalat research reactor. The facility consists of the following parts: collimators, beam stopper, sample holder table, beam catcher, and biological shielding. The construction takes into account the basic parameters associated with the facility, such as adequate thermal neutron flux and cadmium ratio, good signal-to-background condition, small gamma-ray contamination in the beam and appropriately low dose-rate to the operating personnel.
13p vicedric 08-02-2023 4 3 Download
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In this paper, the distribution of absorbed dose components in a polyethylene phantom for BNCT application at Dalat Nuclear Research Reactor (DNRR) were calculated using the MCNP5 code. The configuration of horizontal neutron channel No.2 of the DNRR, which contains a cylindrical collimator with neutron filters of 20-cm Si and 3-cm Bi, was simulated.
7p princessmononoke 29-11-2021 9 1 Download
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The journal of Nuclear science and technology - Volume 10/Number 1 present Determination of thermal neutron flux distribution at the rotary rack served for elemental concentration analysis using the k0-INAA method; Evaluation of slip ratio correlations in two-phase flow; Deposition velocities of some natural radionuclides from the atmosphere at Ninh Thuan and Dong Nai of Vietnam; Determination of recovery efficiency of 137Cs in seawaterusing co-precipitation method...
60p trinhthamhodang1218 14-03-2021 22 2 Download
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In the case of the irradiation position at the rotary rack of the Dalat Nuclear Research Reactor (DNRR), the difference of thermal neutron flux between the bottom (3.541012 n.cm-2 .s-1 ) and the top (1.931012 n.cm-2 .s-1 ) of the 15 cm aluminum container is up to 45%. Therefore, it is necessary to accurately determine above-mentioned parameters in the sample irradiation position. The present paper deals with the determination of the distribution of thermal neutron flux along the sample irradiation container by using 0.1% Au–Al wire activation technique.
10p trinhthamhodang1218 14-03-2021 15 2 Download
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In this paper, three types of operational and industrial absorbers used at research reactors, including Ag-In-Cd alloy, B4C, and Hf are selected for sensitivity analyses. Their integral effects on the main neutronic core parameters important to safety issues are investigated. These parameters are core excess reactivity, shutdown margin, total reactivity worth of control rods, thermal neutron flux, power density distribution, and Power Peaking Factor (PPF). The IAEA 10 MW benchmark core is selected as the case study to verify calculations.
8p minhxaminhyeu5 30-06-2019 22 0 Download
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The presence of crust on the inner walls of metallic ducts impairs transportation because crust completely or partially hinders the passage of fluid to the processing unit and causes damage to equipment connected to the production line. Its localization is crucial. With the development of the electronic imaging system installed at the Argonauta/Nuclear Engineering Institute (IEN)/National Nuclear Energy Commission (CNEN) reactor.
6p minhxaminhyeu4 26-06-2019 22 0 Download
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This study achieved multiple advantageous results: primarily, it will help us perform neutron activation analysis. Next, it will give us the opportunity to produce radio-elements with short half-lives. Am-Be single and multisource (5 sources) experiments were performed within an irradiation facility with a paraffin moderator. The resulting models mainly increase the thermal neutron flux compared to the traditional method with water moderator.
5p minhxaminhyeu4 26-06-2019 16 0 Download
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This paper presents a study on thermal neutron reflection properties of neutron guide for cylinder, spindle, elliptic and parabolic geometries using 241Am-Be neutron source (5.2 Ci) and BF3 detector, whereas neutron guide is important instrument for transportation of neutrons. To this goal, the required inner and outer radii of neutron guide have been calculated to achieve the highest guided thermal neutron flux based on MCNPX Monte Carlo code.
6p minhxaminhyeu3 12-06-2019 9 0 Download
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The neutron flux and Cdratio are 8.72 × 106 n.cm−2 .s−1 and 134, respectively, determined by the gold foil activation method. A new PGNAA system with a HPGe detector of 58% relative efficiency and a digital spectrometer was used to detect prompt gamma rays from the 35Cl(n, γ) 36Cl reaction. In this work, relative intensities of 23 prompt γ-rays have been determined on the filtered thermal neutron beam. The present results are in good agreement with literature values and data from previous measurements.
7p thuyliebe 09-10-2018 31 0 Download