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Journal articles on the topic 'Few-Group Homogenized Cross Sections'

Author: Grafiati

Published: 14 December 2024

Last updated: 31 July 2025

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1

Szames, E., K. Ammar, D. Tomatis, and J. M. Martinez. "FEW-GROUP CROSS SECTIONS MODELING BY ARTIFICIAL NEURAL NETWORKS." EPJ Web of Conferences 247 (2021): 06029. http://dx.doi.org/10.1051/epjconf/202124706029.

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This work deals with the modeling of homogenized few-group cross sections by Artificial Neural Networks (ANN). A comprehensive sensitivity study on data normalization, network architectures and training hyper-parameters specifically for Deep and Shallow Feed Forward ANN is presented. The optimal models in terms of reduction in the library size and training time are compared to multi-linear interpolation on a Cartesian grid. The use case is provided by the OECD-NEA Burn-up Credit Criticality Benchmark [1]. The Pytorch [2] machine learning framework is used.

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2

Tomatis, Daniele. "A multivariate representation of compressed pin-by-pin cross sections." EPJ Nuclear Sciences & Technologies 7 (2021): 8. http://dx.doi.org/10.1051/epjn/2021006.

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Since the 80’s, industrial core calculations employ the two-step scheme based on prior cross sections preparation with few energy groups and in homogenized reference geometries. Spatial homogenization in the fuel assembly quarters is the most frequent calculation option nowadays, relying on efficient nodal solvers using a coarse mesh. Pin-wise reaction rates are then reconstructed by dehomogenization techniques. The future trend of core calculations is moving however toward pin-by-pin explicit representations, where few-group cross sections are homogenized in the single pins at many physical c

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3

Nguyen, Dinh Quoc Dang, and Emiliano Masiello. "Representation of few-group homogenized cross section by multi-variate polynomial regression." EPJ Web of Conferences 302 (2024): 02002. http://dx.doi.org/10.1051/epjconf/202430202002.

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In this paper, a representation of few-group homogenized cross section by multi-variate polynomial regression is presented. The method is applied on the few-group assembly homogenized cross sections of the assembly 22UA from the benchmark X2VVER[1], generated by the lattice transport code APOLLO3®[2], and conducted over a Cartesian grid of parametric state-points. The regression model [3, 4] allow to input a significantly larger number of points for training compared to the number of monomials, thus yielding higher accuracy than polynomial interpolation without being affected by the choice of

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4

Szames, E., K. Ammar, D. Tomatis, and J. M. Martinez. "FEW-GROUP CROSS SECTIONS LIBRARY BY ACTIVE LEARNING WITH SPLINE KERNELS." EPJ Web of Conferences 247 (2021): 06012. http://dx.doi.org/10.1051/epjconf/202124706012.

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This work deals with the representation of homogenized few-groups cross sections libraries by machine learning. A Reproducing Kernel Hilbert Space (RKHS) is used for different Pool Active Learning strategies to obtain an optimal support. Specifically a spline kernel is used and results are compared to multi-linear interpolation as used in industry, discussing the reduction of the library size and of the overall performance. A standard PWR fuel assembly provides the use case (OECD-NEA Burn-up Credit Criticality Benchmark [1]).

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Nguyen, Dinh Q. D., Emiliano Masiello, and Daniele Tomatis. "MPOGen: A Python package to prepare few-group homogenized cross sections for core calculations by APOLLO3®." Nuclear Engineering and Design 417 (February 2024): 112802. http://dx.doi.org/10.1016/j.nucengdes.2023.112802.

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6

Henry, Romain, Yann Périn, Kiril Velkov, and Sergei Pavlovich Nikonov. "3-D COUPLED SIMULATION OF A VVER 1000 WITH PARCS/ATHLET." EPJ Web of Conferences 247 (2021): 06015. http://dx.doi.org/10.1051/epjconf/202124706015.

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A new OECD/NEA benchmark entitled “Reactivity compensation with diluted boron by stepwise insertion of control rod cluster” is starting. This benchmark, based on high quality measurements performed at the NPP Rostov Unit 2, aims to validate and assess high fidelity multi-physics simulation code capabilities. The Benchmark is divided in two phases: assembly wise and pin-by-pin resolution of steady-state and transient multi-physics problems. Multi-physics simulation requires the generation of parametrized few-group cross-sections. This task used to be done with deterministic (2-D) lattice codes,

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7

Galchenko, V. V., А. М. Abdulaev, and І. І. Shlapak. "USING SOFTWARE BASED ON THE MONTE CARLO METHOD FOR RECEIVING THE FEW-GROUP HOMOGENIZED MACROSCOPIC INTERACTION CROSS-SECTIONS." Odes’kyi Politechnichnyi Universytet Pratsi, no. 3(53) (2017): 37–42. http://dx.doi.org/10.15276/opu.3.53.2017.05.

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8

Cao, Liangzhi, Yong Liu, Wei Shen, and Qingming He. "Development of a hybrid method to improve the sensitivity and uncertainty analysis for homogenized few-group cross sections." Journal of Nuclear Science and Technology 54, no. 7 (2017): 769–83. http://dx.doi.org/10.1080/00223131.2017.1315973.

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9

Truffinet, Olivier, Karim Ammar, Jean-Philippe Argaud, Nicolas Gérard Castaing, and Bertrand Bouriquet. "Multi-output gaussian processes for the reconstruction of homogenized cross-sections." EPJ Web of Conferences 302 (2024): 02006. http://dx.doi.org/10.1051/epjconf/202430202006.

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Deterministic nuclear reactor simulators employing the prevalent two-step scheme often generate a substantial amount of intermediate data at the interface of their two subcodes, which can impede the overall performance of the software. The bulk of this data comprises “few-groups homogenized cross-sections” or HXS, which are stored as tabulated multivariate functions and interpolated inside the core simulator. A number of mathematical tools have been studied for this interpolation purpose over the years, but few meet all the challenging requirements of neutronics computation chains: extreme acc

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10

Truffinet, Olivier, Karim Ammar, Jean-Philippe Argaud, Nicolas Gérard Castaing, and Bertrand Bouriquet. "Adaptive sampling of homogenized cross-sections with multi-output gaussian processes." EPJ Web of Conferences 302 (2024): 02010. http://dx.doi.org/10.1051/epjconf/202430202010.

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In another talk submitted to this conference, we presented an efficient new framework based on multi-outputs gaussian processes (MOGP) for the interpolation of few-groups homogenized cross-sections (HXS) inside deterministic core simulators. We indicated that this methodology authorized a principled selection of interpolation points through adaptive sampling. We here develop this idea by trying simple sampling schemes on our problem. In particular, we compare sample scoring functions with and without integration of leave-one-out errors, and obtained with single-output and multi-output gaussian

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11

Guo, Hui, Yuyang Shen, Yiwei Wu, Qufei Song, and Hanyang Gu. "Generating multi-group cross-sections using continuous-energy Monte Carlo method for fast reactor analysis." EPJ Web of Conferences 302 (2024): 02003. http://dx.doi.org/10.1051/epjconf/202430202003.

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The deterministic two-step method, comprising multigroup cross-section generation and core calculation, is widely applied in fast reactor design and analysis. Monte Carlo (MC) methods with continuous energy and fine geometry provide high-precision cross-sections essential for advanced fast reactor neutronics analysis. This paper presents an analysis of integrating MC-generated homogenized cross-sections with various core solvers, demonstrating their effectiveness and potential improvements in fast reactor simulations. For diffusion core calculations, the superhomogénéisation (SPH) technique re

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12

Ardiansyah, H., V. Seker, T. Downar, S. Skutnik, and W. Wieselquist. "Evaluation of PBMR-400 Core Design Steady State Condition with Serpent and AGREE." Journal of Physics: Conference Series 2048, no. 1 (2021): 012024. http://dx.doi.org/10.1088/1742-6596/2048/1/012024.

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Abstract The significant recent advances in computer speed and memory have made possible an increasing fidelity and accuracy in reactor core simulation with minimal increase in the computational burden. This has been important for modeling some of the smaller advanced reactor designs for which simplified approximations such as few groups homogenized diffusion theory are not as accurate as they were for large light water reactor cores. For narrow cylindrical cores with large surface to volume ratios such the Ped Bed Modular Reactor (PBMR), neutron leakage from the core can be significant, parti

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13

Hernandez-Solis, Augusto, Yohannes Molla, Edoaurd Malambu, Alexey Stankovskiy, and Gert Van den Eynde. "VERIFICATION OF THE OpenMC HOMOGENIZED MYRRHA-1.6 CORE MODEL." EPJ Web of Conferences 247 (2021): 04002. http://dx.doi.org/10.1051/epjconf/202124704002.

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The OpenMC code is being employed both as a multi-group nodal macroscopic cross-section generator and a reference multi-group Monte Carlo (MGMC) solution. The aim is to do a neutronic benchmark verification study versus a deterministic model (based on the MYRRHA-1.6 core) performed by the PHISICS simulator. MYRRHA, a novel research accelerator driven system concept that is also foreseen to work as a critical configuration, offers a rich opportunity of testing state-of-the art methods for reactor physics analysis due to its strong heterogeneous configuration utilized for both thermal and fast s

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14

Zhuang, Kun, Xiaobin Tang, and Liangzhi Cao. "Development and verification of a model for generation of MSFR few-group homogenized cross-sections based on a Monte Carlo code OpenMC." Annals of Nuclear Energy 124 (February 2019): 187–97. http://dx.doi.org/10.1016/j.anucene.2018.09.037.

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15

Hwang, Dae Hee, and Ser Gi Hong. "SMALL MODULAR PWR DESIGN FOR TRU RECYCLING WITH McCARD-MASTER TWO-STEP PROCEDURE." EPJ Web of Conferences 247 (2021): 01003. http://dx.doi.org/10.1051/epjconf/202124701003.

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In our previous study, a small modular PWR core was designed for TRU (Transuranics) recycling with multi-recycling scheme with a typical two-step procedure using DeCART2D/MASTER code system in which the lattice analysis for producing homogenized group constant was performed by DeCART2D while whole core analysis was conducted by MASTER code. However, the neutron spectrum hardening of the LWR core loaded with TRU requires validating the multi-group cross section library and resonance self-shielding treatment method in lattice calculation. In this study, a new procedure using McCARD/MASTER was us

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16

Nikitin, E., E. Fridman, K. Mikityuk, S. Radman, and C. Fiorina. "NEUTRONIC MODELLING OF THE FFTF CONTROL ROD WORTH MEASUREMENTS WITH DIFFUSION CODES." EPJ Web of Conferences 247 (2021): 10017. http://dx.doi.org/10.1051/epjconf/202124710017.

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This paper presents an assessment of three deterministic core simulators with the focus on the neutronic performance in steady-state calculations of small Sodium cooled Fast Reactor cores. The selected codes are DYN3D, PARCS and the novel multi-physics solver GeN-Foam. By using these codes, the multi-group diffusion solutions are obtained for the selected twenty control rod worth measurements performed during the isothermal physics tests of the Fast Flux Test Facility (FFTF). The identical set of homogenized few-group cross sections applied in the calculations is generated with the Serpent Mon

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17

Hernández-Solís, Augusto, Christophe Demazière, and Christian Ekberg. "Uncertainty Analyses Applied to the UAM/TMI-1 Lattice Calculations Using the DRAGON (Version 4.05) Code and Based on JENDL-4 and ENDF/B-VII.1 Covariance Data." Science and Technology of Nuclear Installations 2013 (2013): 1–21. http://dx.doi.org/10.1155/2013/437854.

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The OECD/NEA Uncertainty Analysis in Modeling (UAM) expert group organized and launched the UAM benchmark. Its main objective is to perform uncertainty analysis in light water reactor (LWR) predictions at all modeling stages. In this paper, multigroup microscopic cross-sectional uncertainties are propagated through the DRAGON (version 4.05) lattice code in order to perform uncertainty analysis on and 2-group homogenized macroscopic cross-sections. The chosen test case corresponds to the Three Mile Island-1 (TMI-1) lattice, which is a 15 15 pressurized water reactor (PWR) fuel assembly segment

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18

Seubert, A., Y. Périn, and R. Henry. "HIGH-FIDELITY MULTI-PHYSICS PIN-BY-PIN MODEL OF A SVEA-96 OPTIMA2 ASSEMBLY WITH TORT-TD/CTF." EPJ Web of Conferences 247 (2021): 06035. http://dx.doi.org/10.1051/epjconf/202124706035.

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This paper describes the development of a 3-d high-fidelity multi-physics pin-by-pin neu-tronic and sub-channel thermal hydraulic model of a SVEA-96 Optima2 fuel assembly for the coupled code system TORT-TD/CTF. No pin power reconstruction is applied. Detailed descriptions are given on (a) the generation of few-group parameterized pin cell-homogenized cross section data using HELIOS, (b) the 3-d neutronic pin-by-pin and ther-mal-hydraulic sub-channel model of a single SVEA-96 Optima2 assembly and its qualifica-tion by Monte Carlo models using Serpent, (c) coupled steady-state results for a sin

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19

Radaideh, Majdi I., Tomasz Kozlowski, William A. Wieselquist, and Matthew A. Jessee. "Data-Driven and Precursor-Group Uncertainty Propagation of Lattice Kinetic Parameters in UAM Benchmark." Science and Technology of Nuclear Installations 2019 (May 2, 2019): 1–21. http://dx.doi.org/10.1155/2019/3702014.

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A new data-driven sampling-based framework was developed for uncertainty quantification (UQ) of the homogenized kinetic parameters calculated by lattice physics codes such as TRITON and Polaris. In this study, extension of the database for the delayed neutron data (DND) is performed by exploring more delayed neutron experiments and adding additional isotopes/actinides to the data libraries. Afterwards, the framework is utilized to obtain a deeper knowledge of the kinetic parameters’ sensitivity and uncertainty. The kinetic parameters include precursor-group-wise delayed neutron fraction (DNF)

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20

Kim, Wonkyeong, Jinsu Park, Tomasz Kozlowski, Hyun Chul Lee, and Deokjung Lee. "Comparative Neutronics Analysis of DIMPLE S06 Criticality Benchmark with Contemporary Reactor Core Analysis Computer Code Systems." Science and Technology of Nuclear Installations 2015 (2015): 1–11. http://dx.doi.org/10.1155/2015/180979.

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A high-leakage core has been known to be a challenging problem not only for a two-step homogenization approach but also for a direct heterogeneous approach. In this paper the DIMPLE S06 core, which is a small high-leakage core, has been analyzed by a direct heterogeneous modeling approach and by a two-step homogenization modeling approach, using contemporary code systems developed for reactor core analysis. The focus of this work is a comprehensive comparative analysis of the conventional approaches and codes with a small core design, DIMPLE S06 critical experiment. The calculation procedure f

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21

Jang, Seongdong, and Yonghee Kim. "A STUDY OF LEAKAGE-CORRECTED TWO-STEP METHOD BASED ON THE NODAL EQUIVALENCE THEORY FOR FAST REACTOR ANALYSIS." EPJ Web of Conferences 247 (2021): 02026. http://dx.doi.org/10.1051/epjconf/202124702026.

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The conventional two-step method based on the generalized equivalence theory (GET) cannot be directly applied to the fast reactor analysis since the assumption of the space-energy separability is not very valid due to a relatively long neutron mean free path. This study aims to develop a leakage-corrected two-step method for the fast reactor analysis with the aid of the albedo-corrected parameterized equivalence constants (APEC) method. The critical idea of the APEC method is to correct the homogenized group constants (HGCs) including discontinuity factors (DFs) during the nodal calculation th

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22

Botes, Danniëll, and Pavel M. Bokov. "Polynomial interpolation of few-group neutron cross sections on sparse grids." Annals of Nuclear Energy 64 (February 2014): 156–68. http://dx.doi.org/10.1016/j.anucene.2013.09.033.

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23

Kim, Myung H., and A. F. Henry. "Flux-Adjoint Weighted Few-Group Cross Sections Used for Reactor Transient Analysis." Nuclear Science and Engineering 103, no. 3 (1989): 276–82. http://dx.doi.org/10.13182/nse89-a23678.

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24

Du, Xianan, Xuewen Wu, Youqi Zheng, and Yongping Wang. "Reactivity Effect Evaluation of Fast Reactor Based on Angular-Dependent Few-Group Cross Sections Generation." Energies 14, no. 13 (2021): 4042. http://dx.doi.org/10.3390/en14134042.

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Among all the possible occurring reactivity effects of a fast reactor, the situations whereby the control rod was inserted, or the coolant was voided could lead to strong anisotropy of neutron flux distribution, therefore the angular dependence on neutron flux should be considered during the few-group cross-sections generation. Therefore, the purpose of this paper is to compare the influence whether the angular dependence on neutron flux is considered in the calculation of few-group cross sections for the reactivity effect calculation. In the study, the 1-D SN finite difference neutron transpo

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25

Du, Xianan, Liangzhi Cao, Youqi Zheng, and Hongchun Wu. "A hybrid method to generate few-group cross sections for fast reactor analysis." Journal of Nuclear Science and Technology 55, no. 8 (2018): 931–44. http://dx.doi.org/10.1080/00223131.2018.1452650.

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26

Radaideh, Majdi I., Stuti Surani, Daniel O’Grady, and Tomasz Kozlowski. "Shapley effect application for variance-based sensitivity analysis of the few-group cross-sections." Annals of Nuclear Energy 129 (July 2019): 264–79. http://dx.doi.org/10.1016/j.anucene.2019.02.002.

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27

Zhao, Chen, Lianjie Wang, Lei Lou, Bin Zhang, Longlong Zhang, and Bangyang Xia. "Research of the few-group cross-sections calculation based on the software package MOSASAUR." Progress in Nuclear Energy 188 (October 2025): 105884. https://doi.org/10.1016/j.pnucene.2025.105884.

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28

Pautz, Andreas, and Winfried Zwermann. "TRANSIENT CALCULATIONS OF SPERT III EXPERIMENTS." EPJ Web of Conferences 247 (2021): 07017. http://dx.doi.org/10.1051/epjconf/202124707017.

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Cold-startup and hot-standby reactivity accident tests conducted at the SPERT III E-core research reactor are analysed with the coupled neutron-kinetic/thermal-hydraulic code system DYN3D-ATHLET. Homogenised 2-group cross sections for DYN3D are thereby generated with the Monte Carlo neutron transport code Serpent 2 in combination with the ENDF/B-VII.1 cross section library. Results in terms of maximum power, energy release, and reactivity compensation are in good agreement with the experimental values. The time-dependent contributions to the reactivity feedback are investigated for both a cold

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29

Nguyen, Tung Dong Cao, Hyunsuk Lee, Xianan Du, Vutheam Dos, Tuan Quoc Tran, and Deokjung Lee. "MACROSCOPIC CROSS SECTIONS GENERATION BY MONTE CARLO CODE MCS FOR FAST REACTOR ANALYSIS." EPJ Web of Conferences 247 (2021): 02007. http://dx.doi.org/10.1051/epjconf/202124702007.

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Recent researches have become more interested in the feasibility of using Monte Carlo (MC) code to generate multi-group (MG) cross sections (XSs) for fast reactor analysis using nodal diffusion codes. The current study, therefore, presents a brief methodology for MG XSs generation by the in-house UNIST MC code MCS, which can be compatibly utilized in nodal diffusion codes, PARCS and RAST-K. The applicability of the methodology is quantified on the sodium fast reactor (SFR) ABR-1000 design with a metallic fuel from the OECD/NEA SRF benchmark. The few-group XSs generated by MCS with a two-dimens

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30

Shchurovskaya, M. V., N. I. Geraskin, M. S. Siddiquee, and A. E. Kruglikov. "Few group cross sections generation using MCU-PTR and Serpent for diffusion calculation of light water research reactor." Journal of Physics: Conference Series 1133 (November 2018): 012002. http://dx.doi.org/10.1088/1742-6596/1133/1/012002.

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31

Shchurovskaya, M. V., N. I. Geraskin, and A. E. Kruglikov. "Comparison of research reactor full-core diffusion calculations with few-group cross sections generated using Serpent and MCU-PTR." Annals of Nuclear Energy 141 (June 2020): 107361. http://dx.doi.org/10.1016/j.anucene.2020.107361.

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32

Maragkos, Fotis, Michael Kokkoris, and Anastasios Lagogiannis. "MottCalc: A new tool for calculating Mott scattering differential cross sections for analytical purposes." HNPS Proceedings 27 (April 17, 2020): 112. http://dx.doi.org/10.12681/hnps.2986.

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In the last few years, the popularity of ERDA applications has soared along with the implementation of time of flight (TOF) type measurements. However, ERDA and other forward scattering IBA techniques suffer from the possibility of the occurence of Mott scattering. This leads to deviations in the elastic differential cross sections which in turn demand special care in the treatment of the obtained experimental spectra. To address this issue, a new code has been developed, called MottCalc (Mott Calculator). Based on the analytical formula, first developed by Mott, which describes the phenomenon

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33

Zherdev, Gennady, Tamara Kislitsyna, and Mark Nikolayev. "ROCOCO system of combined neutron constants – current status and results of testing using geometrical module of the MMK code." Nuclear Energy and Technology 4, no. 3 (2018): 217–22. http://dx.doi.org/10.3897/nucet.4.31861.

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Results of studies aimed at the further refinement of the ROCOCO system (routine for calculation and organization of combined constants including cross-sections in group and subgroup representation with detailed description of energy dependence of neutron cross-sections) (Zherdev et al. 2018, Kislitsina et al. 2016) are presented in the paper. Inclusion of this system as a physical module into a set of Monte Carlo calculation codes with OOBG geometric module from the MMK code (Zherdev et al. 2003) is discussed. OOBG module is designed for calculation of neutron multiplication systems with hete

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Zherdev, Gennady M., Tamara S. Kislitsyna, and Mark N. Nikolayev. "ROCOCO system of combined neutron constants – current status and results of testing using geometrical module of the MMK code." Nuclear Energy and Technology 4, no. (3) (2018): 217–22. https://doi.org/10.3897/nucet.4.31861.

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Results of studies aimed at the further refinement of the ROCOCO system (routine for calculation and organization of combined constants including cross-sections in group and subgroup representation with detailed description of energy dependence of neutron cross-sections) (Zherdev et al. 2018, Kislitsina and Nikolaev 2016) are presented in the paper. Inclusion of this system as a physical module into a set of Monte Carlo calculation codes with OOBG geometric module from the MMK code (Zherdev et al. 2003) is discussed. OOBG module is designed for calculation of neutron multiplication systems wit

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Haeberli, W. "Parity violation in proton scattering: low energy region." Canadian Journal of Physics 66, no. 6 (1988): 485–94. http://dx.doi.org/10.1139/p88-080.

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Measurements of the parity-violating longitudinal analyzing power, Az, in the scattering of low-energy protons (Ep < 50 MeV) are reviewed. The experiments are based on the determination of the relative scattering cross sections σ+ and σ− for incident protons of positive and hegative helicity, respectively. The first results were reported from Los Alamos, where a significant analyzing power [Az = (−1.7 ± 0.8) × 10−7] was found for p–p scattering at 15 MeV. All other results are for a proton energy near 45 MeV, primarily by the group working at Schweizerisches Institut für Nuklearforschung, w

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36

Prasad Joshi, Arun, Neer Shobha Chitrakar, Jitendra Pariyar, Isha Shrestha, Rima Maharjan, and Pabitra Maharjan. "Perinatal Outcome: A Comparative Study between Emergency and Elective Caesarean Section at A Tertiary Care Hospital." Journal of Perinatal Society of Nepal 1, no. 1 (2023): 1–5. http://dx.doi.org/10.59881/jpeson1.

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Introduction: Caesarean delivery is the most commonly performed lifesaving procedure in obstetrics. Caesarean section can be done in emergency and elective basis. There has been rising trend of caesarean section over the last few decades. Both the caesarean sections are associated with fetal risks than vaginal delivery. Objectives: To assess and compare the perinatal outcomes of emergency and elective caesarean sections. Methods: It was a cross-sectional comparative study done in Civil Service Hospital of Nepal over the period of one year starting from January 2021 to December 2021

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Lee, Do Kyung, Jun Ho Kim, Byung Hoon Lee, et al. "Influence of Graft Bending Angle on Femoral Tunnel Widening After Double-Bundle ACL Reconstruction: Comparison of Transportal and Outside-In Techniques." Orthopaedic Journal of Sports Medicine 9, no. 10 (2021): 232596712110357. http://dx.doi.org/10.1177/23259671211035780.

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Background: Previous studies have suggested that increased mechanical stress due to acute graft bending angle (GBA) is associated with tunnel widening and graft failure after anterior cruciate ligament (ACL) reconstruction. Few studies have compared the GBA between the outside-in (OI) and the transportal (TP) techniques. Purpose: To evaluate the influence of GBA on clinical outcomes and tunnel widening after ACL reconstruction with OI versus TP technique. Study Design: Cohort study; Level of evidence, 3. Methods: Included in the study were 56 patients who underwent double-bundle ACL reconstruc

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Bertulani, Carlos A., Francis W. Hall, and Benjamin I. Santoyo. "Big Bang nucleosynthesis as a probe of new physics." EPJ Web of Conferences 275 (2023): 01003. http://dx.doi.org/10.1051/epjconf/202327501003.

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The Big Bang Nucleosynthesis (BBN) model is a cornerstone for the understanding of the evolution of the early universe, making seminal predictions that are in outstanding agreement with the present observation of light element abundances in the universe. Perhaps, the only remaining issue to be solved by theory is the so-called “lithium abundance problem". Dedicated experimental efforts to measure the relevant nuclear cross sections used as input of the model have lead to an increased level of accuracy in the prediction of the light element primordial abundances. The rise of indirect experiment

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Vera von Bargen, Helga, María Espinosa Serrano, Daniel Martin Navarrete, et al. "Analysis of prevalence and sociodemographic conditions among women in labor with and without COVID-19 in public hospitals in Chile." Journal of Perinatal Medicine 50, no. 2 (2021): 132–38. http://dx.doi.org/10.1515/jpm-2021-0286.

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Abstract Objectives The SARS-CoV-2 virus continues wreaking worldwide havoc on health and between March and August 2020, the first outbreak of COVID-19 hit Chile. The pregnant population is especially vulnerable to infection. Studies have been published that associate socioeconomic status, overcrowding, and poverty with a higher prevalence of SARS-CoV-2 infection. There are few studies about the development of this pandemic in Latin American countries so far. This study seeks to show the prevalence and sociodemographic and perinatal characteristics in pregnant women at the time of delivery, co

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Ovdiienko, Yu, M. Yeremenko, V. Khalimonchuk, A. Kuchin, and Yu Bilodid. "Effect of Fuel Burnup History on Neutronic Characteristics of WWER-1000 Core." Nuclear and Radiation Safety, no. 3(63) (September 1, 2014): 14–18. http://dx.doi.org/10.32918/nrs.2014.3(63).03.

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In preparation of few-group cross-section libraries to be used in WWER macro-calculations, change in the nuclide composition during fuel burnup is commonly defined under invariable characteristics, averaged over the entire core (power, fuel and moderator temperature, moderator density etc.). In reality, conditions of fuel burnup are changing and this factor affects the fuel nuclide composition (the so-called spectral history effect). To account for real burnup history, it is necessary to take into consideration the dependence of cross-sections not only on burnup but also on history of neutron

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Woytek, Bernhard, Marta Rodrigues, Federica Cappa, Manfred Schreiner, Martin Radtke, and Uwe Reinholz. "Imitations of Roman Republican Denarii: New Metallurgical Data." American Journal of Numismatics. Second Series 24 (2012) (December 21, 2012): 133–62. https://doi.org/10.5281/zenodo.7932877.

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This article presents the results of scientific analyses performed on nine ancient imitations of Roman Republican silver denarii, which are part of a group commonly referred to as “Geto-Dacian” imitations, and discusses the data in a broader context. The coins were dissected and analyzed for their composition in the core with synchrotron micro X-ray fluorescence analysis (μ-SRXRF); their microstructure was examined with a scanning electron microscope (SEM) using backscattered electrons. Micrographs of all the cross-sections are published. The majority of the coins were found to

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Singhvi, Shreyans D., Preksha T. Singh, and Gautam Bhandari. "Assessment of multiple factors affecting intelligence quotient of children of rural and urban areas of Rajasthan, India." International Journal of Research in Medical Sciences 8, no. 7 (2020): 2557. http://dx.doi.org/10.18203/2320-6012.ijrms20202895.

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Background: Children are the future of our country and hence their mental and physical wellbeing should be our upmost priority. Undernutrition is a major public health problem in our country and is one of the most common reasons for morbidity and mortality in children under 5yrs of age. The first few years of life are particularly important because vital development occurs in all domains. Therefore, this study has aimed to study the Intelligence Quotient (IQ) of the children of the age group 3-5 in urban and rural areas and study the factors associated with it.Methods: A cross section study of

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Honj, Renato M., André M. Vaz-dos-Santos, and Carmen Lúcia D. B. Rossi-Wongtschowsk. "Identification of the stages of ovarian maturation of the Argentine hake Merluccius hubbsi Marini, 1933 (Teleostei: Merlucciidae): advantages and disadvantages of the use of the macroscopic and microscopic scales." Neotropical Ichthyology 4, no. 3 (2006): 329–37. http://dx.doi.org/10.1590/s1679-62252006000300004.

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The Argentine hake Merluccius hubbsi is a demersal-pelagic species on which few studies have been undertaken, despite its importance for the fisheries of the South-Southeastern Brazilian region, . The species is the most important commercial fishery resource in Uruguay and Argentina, where several studies have permitted the proper monitoring of the species. The ovarian maturation of the Argentine hake is analysed in this study. A scale of maturation is presented in the light of the oocyte development and the use of macro and microscopic scales of ovarian maturation are compared. It was detecte

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Virk, Punit, Samara Laskin, Rebecca Gokiert, et al. "MyHEARTSMAP: development and evaluation of a psychosocial self-assessment tool, for and by youth." BMJ Paediatrics Open 3, no. 1 (2019): e000493. http://dx.doi.org/10.1136/bmjpo-2019-000493.

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BackgroundPaediatric mental health-related visits to the emergency department are rising. However, few tools exist to identify concerns early and connect youth with appropriate mental healthcare. Our objective was to develop a digital youth psychosocial assessment and management tool (MyHEARTSMAP) and evaluate its inter-rater reliability when self-administered by a community-based sample of youth and parents.MethodsWe conducted a multiphasic, multimethod study. In phase 1, focus group sessions were used to inform tool development, through an iterative modification process. In phase 2, a cross-

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Biradar, Vidyadhar G., S. S. Hebbal, and S. M. Qutubuddin. "Ergonomic Risk Identification and Postural Analysis in Electrical Transformers Manufacturing Company located in Southern India." International Journal of Occupational Safety and Health 14, no. 2 (2024): 144–51. http://dx.doi.org/10.3126/ijosh.v14i2.53692.

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Introduction: Musculoskeletal disorders are the major factors resulting in discomfort at work in manufacturing industries to workers and these conditions contribute to the poor health of the workforce, subsequently to lower productivity. Therefore, the design of a workstation based on Ergonomic principles is becoming significant to reduce the effects of MSD. This study aimed to identify and assess the ergonomic risks associated with the work tasks in the company through posture analysis and develop recommendations for reducing those risks. Methods: About 36 manufacturing workers from five sect

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Fortunato, L., J. Casal, W. Horiuchi, et al. "Advances on clusters and correlations in nuclear structure and reactions." Journal of Physics: Conference Series 2586, no. 1 (2023): 012030. http://dx.doi.org/10.1088/1742-6596/2586/1/012030.

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Abstract Recent advances obtained in the last few years by the Theoretical Nuclear Physics group in Padova with various collaborators on alpha-cluster models and on nuclear correlations in stable and unstable light nuclei are reviewed in this contribution. The algebraic cluster model assumes triangular and tetrahedral arrangement of α particles for 12C and 16O respectively. The description of the low-lying states achieved in this model, that is a consequence of the requirement of discrete symmetries, is extremely good. We have made several calculations of α-transfer form factors and reaction c

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Pinem, Surian, Sukmanto Dibyo, Wahid Luthfi, Veronica Indriati Sri Wardhani, and Donny Hartanto. "An Improved Steady-State and Transient Analysis of the RSG-GAS Reactor Core under RIA Conditions Using MTR-DYN and EUREKA-2/RR Codes." Science and Technology of Nuclear Installations 2022 (July 30, 2022): 1–12. http://dx.doi.org/10.1155/2022/6030504.

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Steady-state and transient analysis of reactor core under Reactivity-Initiated Accident (RIA) conditions are important for reactor operation safety. The reactor dynamics are influenced by neutronic and thermal-hydraulic aspects of the core. In this study, steady-state and transient analysis under RIA conditions of the RSG-GAS multipurpose reactor was carried out using MTR-DYN and EUREKA-2/RR programs. Neutronic calculations were performed using a few group cross-sections generated by Serpent 2 with the latest cross-section data ENDF/B-VIII.0. Steady-state conditions were carried out with a nom

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Pellinen-Wannberg, A., A. Westman, G. Wannberg, and K. Kaila. "Meteor fluxes and visual magnitudes from EISCAT radar event rates: a comparison with cross-section based magnitude estimates and optical data." Annales Geophysicae 16, no. 11 (1998): 1475–85. http://dx.doi.org/10.1007/s00585-998-1475-x.

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Abstract. Incoherent scatter radars (ISR) are versatile instruments for continuous monitoring of ionisation processes in the Earth's atmosphere. EISCAT, The European Incoherent Scatter facility has proven effective also in meteor studies. The time resolution of the radar can be reduced to a few milliseconds, sufficient to resolve the passage of individual meteors through the narrow ISR beam. Methods for group and phase velocity determination of the meteoroids and the discrepancy between the results related to the target behaviour are presented. The radar cross sections of echoes associated wit

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Olsen, T., S. Sass, N. Li, and J. Duman. "Factors contributing to seasonal increases in inoculative freezing resistance in overwintering fire-colored beetle larvae dendroides canadensis." Journal of Experimental Biology 201, no. 10 (1998): 1585–94. http://dx.doi.org/10.1242/jeb.201.10.1585.

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The insects and microarthropods that vary seasonally in susceptibility to cross-cuticular inoculation by external ice (inoculative freezing) represent a phylogenetically diverse group; however, few studies have explored possible mechanisms experimentally. This study documents seasonally variable inoculative freezing resistance in Dendroides canadensis beetle larvae and combines immunofluorescence, in vivo removal of epicuticular lipids and in vitro chamber studies to explore the roles of seasonal modification in the cuticle and in epidermal and hemolymph antifreeze proteins (AFPs). Seasonal cu

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Bassi, Madu M., Dahiru Isa, and Clement Pembi. "Development of Nggwaba Orthography: Syllabic, Phonemic and Tones Patterns." Journal of Natural Language and Linguistics 2, no. 1 (2024): 135–42. http://dx.doi.org/10.54536/jnll.v2i1.3484.

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Nggwaba has been described as an Afro-asiatic language. Further classification situates it in the Chadic group precisely Biu-Mandara. The language is spoken in Gombi and Hong Local Government Areas of Adamawa State, North-east, Nigeria. It has been noticed that the language has largely been under-documented and under-investigated. The estimated number of people who speak the language is less than 1000. This paper presents the orthography and a preliminary analysis of a few aspects of the phonology of the language for the early primary education level. It became necessary to study, develop and

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