Neutron cross section
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The W isotopic compositions have been investigated within the classical approach to the sprocess nucleosynthesis. The Maxwellian averaged neutron capture cross-sections (MACS) adopted in the calculation are obtained from the TALYS-1.9 code with four nuclear level density models: the constant temperature plus Fermi gas, the back-shifted Fermi gas, the generalised superfluid, and the microscopic method of Goriely.
7p vispiderman 15-06-2023 3 3 Download
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Nuclear shell structure and magic numbers are important guides for understanding the overall properties of atomic nuclei, the widespread development of state-of-the-art experimental methods giving many new opportunities for studies of exotic nuclei. This work presents measurements of cross sections of nucleon-removal reactions from neutron-rich copper to gallium isotopes.
8p vicedric 08-02-2023 4 3 Download
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This paper presents a model development of the Dalat nuclear research reactor (DNRR) with the Serpent 2 Monte Carlo code. The purpose is to prepare the DNRR Serpent 2 model for performing fuel burnup calculations of the DNRR as well as for generating multi-group neutron cross sections to be further used in the kinetics calculations of the DNRR with a 3D reactor kinetics code.
9p vicedric 08-02-2023 3 3 Download
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The comparative results generally show a good agreement between TRITON and Serpent with the benchmark data, indicating that the TRITON and Serpent models developed herein for the PWR MOX assemblies can be applied to group constant generation to be further used in transient analyses of PWR MOX fueled cores.
5p visnape 30-01-2023 7 4 Download
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Neutron noise calculated from the neutron noise equation in the frequency domain is governed by the cross section and kinetic parameters. Deterministic and stochastic methods to obtain the sensitivity coefficient of neutron noise with respect to the abovementioned parameters are proposed.
6p vironald 15-12-2022 10 4 Download
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In this study, the SCALE/TRITON code (based on deterministic method) and the Serpent 2 code (based on Monte Carlo method) were utilized to prepare the group constants of the pressurized water reactor (PWR) mixed-oxide (MOX) fuel assemblies for transient analyses of PWR MOX fueled cores in normal operation and control rod ejection accident condition with 3D reactor kinetics codes.
10p meyerowitz 25-12-2021 7 0 Download
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These filtered neutron beams have been applied efficiently for experimental researches on neutron total and capture cross sections measurements, and elemental analysis in various kinds of samples based on the prompt gamma neutron activation analysis method. This paper reviews the progress of filtered neutron beams development and its applications for past many years at the Dalat nuclear research reactor.
8p trinhthamhodang1218 14-03-2021 6 1 Download
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This paper presents a model development of the Dalat Nuclear Research Reactor (DNRR) loaded with low enriched uranium (LEU) fuel using the Serpent 2 Monte Carlo code. The purpose is to prepare the DNRR Serpent 2 model for performing fuel burnup calculations of the DNRR as well as for generating multi-group neutron cross sections to be further used in the kinetics calculations of the DNRR with a 3D reactor kinetics code.
9p trinhthamhodang1218 14-03-2021 5 1 Download
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This paper presents a Bayesian approach based on integral experiments to create correlations which do not appear with differential data. Some quantities such as the fission cross section (s), neutron multiplicity (n¯p), neutron spectra (x), etc. are usually neither modeled together nor measured in coincidence, thus there is no correlation matrices in evaluated nuclear data libraries.
8p christabelhuynh 30-05-2020 13 0 Download
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In nuclear safety research, the quality of the results of simulation codes is widely determined by the reactor design and safe operation, and the description of neutron transport in the reactor core is a feature of particular importance.
14p christabelhuynh 30-05-2020 37 0 Download
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These studies are performed in the general framework of transient coupled calculations with accurate neutron kinetics models. This kind of application requires a modeling of the influence on the neutronics of the macroscopic cross-section evolution.
8p christabelhuynh 30-05-2020 3 0 Download
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This article shows how the most recent gadolinium cross sections evaluations appear inadequate to provide accurate criticality calculations for a system with gadolinium fuel pins. In this article, a sensitivity and uncertainty analysis (S/U) has been performed to investigate the effect of gadolinium odd isotopes nuclear cross sections data on the multiplication factor of some LWR fuel assemblies.
11p christabelhuynh 30-05-2020 12 1 Download
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Concerns within the nuclear data community led to substantial increases of Neutron Data Standards (NDS) uncertainties from its previous to the current version. For example, those associated with the NDS reference cross section 239Pu(n,f) increased from 0.6–1.6% to 1.3–1.7% from 0.1–20 MeV.
22p christabelhuynh 29-05-2020 12 0 Download
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A correlated sampling technique has been implemented to estimate the impact of cross section modifications on the neutron transport and in Monte Carlo simulations in one single calculation. This implementation has been coupled to a Total Monte Carlo approach which consists in propagating nuclear data uncertainties with random cross section files.
9p christabelhuynh 29-05-2020 5 0 Download
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In the current paper, we investigate the application of the Equivalent Generalized Perturbation Theory (EGPT) to derive trends and associated covariances on the neutron capture cross section of one major fission product for both light water reactors and sodium-cooled fast reactors which is Rhodium-103.
9p christabelhuynh 29-05-2020 12 0 Download
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The deterministic simple least square (LS) approach is employed in the covariance analysis of the total neutron cross section (n,tot) calculated by a microscopic optical potential, CTOM, which is based on a fundamental theory Dirac Brueckner Hartree Fock.
6p christabelhuynh 29-05-2020 3 0 Download
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Key reactions have been selected to compare JEFF-3.3 (CIELO 2) and IAEA CIELO (CIELO 1) evaluated nuclear data files for neutron induced reactions on 235U and 238U targets. IAEA CIELO evaluation uses reaction models to construct the evaluation prior, but strongly relied on differential data including all reaction cross sections fitted within the IAEA Neutron Standards project.
5p christabelhuynh 29-05-2020 10 0 Download
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This paper presents a study of the impact of the nuclear data (cross sections, neutron emission and spectra) on different quantities for spent nuclear fuels (SNF) from Swiss power plants: activities, decay heat, neutron and gamma sources and isotopic vectors.
15p christabelhuynh 29-05-2020 4 1 Download
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Instead of running hundreds or thousands of neutronics calculations, we therefore investigate the possibility to take those many cross-section file samples and perform ‘cheap’ sensitivity perturbation calculations. This is efficiently possible with the NEA Nuclear Data Sensitivity Tool (NDaST) and this process we name the half Monte Carlo method (HMM).
8p christabelhuynh 29-05-2020 9 0 Download
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A template for estimating uncertainties (unc.) of measured neutron-induced fission, (n,f), cross-sections (cs) is presented. This preliminary template not only lists all expected unc. sources but also supplies ranges of unc., estimates for correlations between unc. of the same and different experiments which can be used if the information is nonexistent.
9p christabelhuynh 29-05-2020 5 0 Download