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Journal articles on the topic 'Core'

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Author: Grafiati

Published: 4 June 2021

Last updated: 29 July 2024

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1

Goričanec, Tanja, Domen Kotnik, Žiga Štancar, Luka Snoj, and Marjan Kromar. "Predicting Ex-core Detector Response in a PWR with Monte Carlo Neutron Transport Methods." EPJ Web of Conferences 225 (2020): 03007. http://dx.doi.org/10.1051/epjconf/202022503007.

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An approach for calculating ex-core detector response using Monte Carlo code MCNP was developed. As a first step towards ex-core detector response prediction a detailed MCNP model of the reactor core was made. A script called McCord was developed as a link between deterministic program package CORD-2 and Monte Carlo code MCNP. It automatically generates an MCNP input from the CORD-2 data. A detailed MCNP core model was used to calculate 3D power distributions inside the core. Calculated power distributions were verified by comparison to the CORD-2 calculations, which is currently used for core design calculation verification of the Krško nuclea power plant. For the hot zero power configuration, the deviations are within 3 % for majority of fuel assemblies and slightly higher for fuel assemblies located at the core periphery. The computational model was further verified by comparing the calculated control rod worth to the CORD-2 results. The deviations were within 50 pcm and considered acceptable. The research will in future be supplemented with the in-core and ex-core detector signal calculations and neutron transport outside the reactor core.

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2

HURMAN, Ivan, Kira BOBROVNIKOVA, Leonid BEDRATYUK, and Hanna BEDRATYUK. "APPROACH FOR CODE ANALYSIS TO ESTIMATE POWER CONSUMPTION OF CUDA CORE." Herald of Khmelnytskyi National University. Technical sciences 217, no. 1 (February 23, 2023): 67–73. http://dx.doi.org/10.31891/2307-5732-2023-317-1-67-73.

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The graphics processing unit is a popular computing device for achieving exascale performance in high-performance computing programs, which is used not only in graphics tasks, but also in computational tasks such as machine learning, scientific computing, and cryptography. With the help of a graphics processor, you can achieve significant speed and performance compared to the central processing unit. CUDA, Compute Unified Device Architecture, a graphics processing unit software development platform, allows developers to use the high-performance computing capabilities of graphics processing units to solve problems traditionally handled by central processing units. Even though the graphics processing unit has a relatively high power to performance ratio, it consumes a significant amount of power during computing. The paper proposes an approach for code analysis to estimate power consumption of CUDA core to improve the power efficiency of applications focused on computing on graphics processing units. The proposed approach makes it possible to estimate the power consumption of such applications without the need to run them on physical devices. The proposed approach is based on static analysis of the CUDA program and machine learning methods. To evaluate the effectiveness of the proposed approach, three graphics processing unit architectures were used: NVIDIA PASCAL, NVIDIA TURING, and NVIDIA AMPERE. The results of the experiments showed that for the NVIDIA AMPERE architecture, the proposed approach using decision trees makes it possible to achieve a determination coefficient of 0.9173. The results obtained confirm the effectiveness of the proposed code analysis method for estimating the power consumption of the CUDA core. This method can be useful for CUDA developers who want to improve the efficiency and power efficiency of their programs.

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3

Shepherd, Iain, Tim Haste, Naouma Kourti, Francesco Oriolo, Mario Leonardi, Jürgen Knorr, Sabine Kretschmer, et al. "Investigation of core degradation (COBE)." Nuclear Engineering and Design 209, no. 1-3 (November 2001): 107–16. http://dx.doi.org/10.1016/s0029-5493(01)00393-4.

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4

Johzaki, T., H. Sakagami, H. Nagatomo, and K. Mima. "Holistic Simulation for FIREX Project with FI3." Laser and Particle Beams 25, no. 4 (October 15, 2007): 621–29. http://dx.doi.org/10.1017/s0263034607000730.

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AbstractIn fast ignition research, the clarification of core heating mechanism is one of the most critical issues. To understand and identify the crucial physics in fast heating, we developed the fast ignition integrated interconnecting code FI3 and carried out the core heating simulations for fast heating experiments with cone-guided targets. It was found that the scale length of the pre-plasma at the inner-surface of the cone and the density gap at the contact surface between the cone tip and the imploded core plasma strongly affect the efficiency of core heating. In the case of heating laser with intensity of 1020 W/cm2 and duration of 1 ps, the pre-plasma scale length of 1.5 µm is optimum for the core heating; the dense core is heated up to 0.86 keV. In the double scale length case (long scale of ~5 µm in underdense region and short scale of ~ 1 µm in overdense region), of which generation due to the pre-pulse irradiation of heating pulse is observed at the radiation–hydro simulations, the dense core is heated more efficiently than single short scale length cases. The contribution of fast ions to the core heating is also discussed.

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5

Bauschlicher, Charles W., Stephen R. Langhoff, and Peter R. Taylor. "Core–core and core–valence correlation." Journal of Chemical Physics 88, no. 4 (February 15, 1988): 2540–46. http://dx.doi.org/10.1063/1.454032.

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6

Perić, Dunja, Gyuhyeong Goh, Javad Saeidaskari, Arash Saeidi Rashk Olia, and Pooyan Ayar. "Development of Prediction Models for Performance of Flexible Pavements in Kansas with Emphasis on the Effects of Subgrade and Unbound Layers." Sustainability 14, no. 15 (July 22, 2022): 9020. http://dx.doi.org/10.3390/su14159020.

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This study resulted from the need for better consideration of subgrade and unbound layers on the performance of flexible pavements in Kansas. Thus, the main objective was to develop pavement performance prediction models with emphasis on the effects of subgrade and unbound layers. To this end, pavement distress data, which were collected over several years across the state of Kansas, including rutting, fatigue cracking, transverse cracking, roughness and core analysis, served as the input data into statistical models. The effects of subgrade and unbound layers were represented by the corresponding results of dynamic cone penetrometer (DCP) tests and thickness of the unbound layer. In addition, traffic volume was represented by average annual daily truck traffic (AADTT). Multiple statistical analyses identified positive correlations of dynamic cone penetration index (DPI) and rate of total rutting, and DPI and percent of good core. Negative correlation was discovered between DPI and fatigue cracking code one, and DPI and percent of poor core. AADTT was positively correlated with transverse cracking codes one and two while it had no correlation with transverse cracking code zero. Thickness of the unbound layer was negatively correlated with pavement roughness and percent of poor core, while it was positively correlated with the percent of good core. Finally, the recommendation for minimum acceptable value of California bearing ratio (CBR) was provided based on the correlation between DPI and rate of change of rutting code. The recommendation enables the selection of a CBR value based on the number of years required for unit increase in the rutting code.

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7

SAKAGAMI, H., T. JOHZAKI, H. NAGATOMO, and K. MIMA. "Fast ignition integrated interconnecting code project for cone-guided targets." Laser and Particle Beams 24, no. 1 (March 2006): 191–98. http://dx.doi.org/10.1017/s0263034606050762.

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It was reported that the fuel core was heated up to ∼0.8 keV in the fast ignition experiments with cone-guided targets, but they could not theoretically explain heating mechanisms and achievement of such high temperature. Thus simulations should play an important role in estimating the scheme performance, and we must simulate each phenomenon with individual codes and integrate them under the fast ignition integrated interconnecting code project. In the previous integrated simulations, fast electrons generated by the laser-plasma interaction were too hot to efficiently heat the core and we got only 0.096 keV rise of temperature. Including the density gap at the contact surface between the cone tip and the imploded plasma, the period of core heating became longer and the core was heated by 0.162 keV, ∼ 69% higher increment compared with ignoring the density gap effect.

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8

Ashmore, Jamile A. "CORE Report: Dallas CORE." Obesity Management 1, no. 6 (December 2005): 261. http://dx.doi.org/10.1089/obe.2005.1.261.

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9

ISHIZU, Tomoko, Hiroshi ENDO, Isao TATEWAKI, Toshihisa YAMAMOTO, and Noriyuki SHIRAKAWA. "ICONE19-43559 Development of Integrated Core Disruptive Accident Analysis Code for FBR : ASTERIA-FBR." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2011.19 (2011): _ICONE1943. http://dx.doi.org/10.1299/jsmeicone.2011.19._icone1943_227.

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10

Tsuji, Nobumasa, and Kazutaka Ohashi. "ICONE23-1203 Development of seismic analysis model for HTGR core on commercial FEM code." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2015.23 (2015): _ICONE23–1—_ICONE23–1. http://dx.doi.org/10.1299/jsmeicone.2015.23._icone23-1_105.

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11

Kułaga, Tomasz, Jacek Tabor, and Łukasz Struski. "Cone-fields without constant orbit core dimension." Discrete and Continuous Dynamical Systems 32, no. 10 (May 2012): 3651–64. http://dx.doi.org/10.3934/dcds.2012.32.3651.

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12

DeVivo, M., F. Biering-Sørensen, S. Charlifue, V. Noonan, M. Post, T. Stripling, and P. Wing. "International Spinal Cord Injury Core Data Set." Spinal Cord 44, no. 9 (September 2006): 535–40. http://dx.doi.org/10.1038/sj.sc.3101958.

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13

Wadhwa, Nalin, Jui Pradhan, Atharv Sonwane, Surya Prakash Sahu, Nagarajan Natarajan, Aditya Kanade, Suresh Parthasarathy, and Sriram Rajamani. "CORE: Resolving Code Quality Issues using LLMs." Proceedings of the ACM on Software Engineering 1, FSE (July 12, 2024): 789–811. http://dx.doi.org/10.1145/3643762.

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As software projects progress, quality of code assumes paramount importance as it affects reliability, maintainability and security of software. For this reason, static analysis tools are used in developer workflows to flag code quality issues. However, developers need to spend extra efforts to revise their code to improve code quality based on the tool findings. In this work, we investigate the use of (instruction-following) large language models (LLMs) to assist developers in revising code to resolve code quality issues. We present a tool, CORE (short for COde REvisions), architected using a pair of LLMs organized as a duo comprised of a proposer and a ranker. Providers of static analysis tools recommend ways to mitigate the tool warnings and developers follow them to revise their code. The proposer LLM of CORE takes the same set of recommendations and applies them to generate candidate code revisions. The candidates which pass the static quality checks are retained. However, the LLM may introduce subtle, unintended functionality changes which may go un-detected by the static analysis. The ranker LLM evaluates the changes made by the proposer using a rubric that closely follows the acceptance criteria that a developer would enforce. CORE uses the scores assigned by the ranker LLM to rank the candidate revisions before presenting them to the developer. We conduct a variety of experiments on two public benchmarks to show the ability of CORE: (1) to generate code revisions acceptable to both static analysis tools and human reviewers (the latter evaluated with user study on a subset of the Python benchmark), (2) to reduce human review efforts by detecting and eliminating revisions with unintended changes, (3) to readily work across multiple languages (Python and Java), static analysis tools (CodeQL and SonarQube) and quality checks (52 and 10 checks, respectively), and (4) to achieve fix rate comparable to a rule-based automated program repair tool but with much smaller engineering efforts (on the Java benchmark). CORE could revise 59.2% Python files (across 52 quality checks) so that they pass scrutiny by both a tool and a human reviewer. The ranker LLM reduced false positives by 25.8% in these cases. CORE produced revisions that passed the static analysis tool in 76.8% Java files (across 10 quality checks) comparable to 78.3% of a specialized program repair tool, with significantly much less engineering efforts. We release code, data, and supplementary material publicly at http://aka.ms/COREMSRI.

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14

Mitkov, Svetlomir, Ivan Spasov, and Nikola Kolev. "Thermal-hydraulic analysis of a VVER-1000 core in MSLB conditions." E3S Web of Conferences 327 (2021): 01013. http://dx.doi.org/10.1051/e3sconf/202132701013.

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The objective of this paper is to analyze the ability of a VVER-1000 core and its control system to cope with a hypothetical main steam line break (MSLB) accident in case of multiple equipment failures. The study involves the use of advanced 3D core calculation models benchmarked and validated for reactivity accidents in preceding studies. A MSLB core boundary condition problem is solved on a coarse (nodal) mesh with the coupled COBAYA/CTF neutronic/thermal hydraulic codes. The core thermal-hydraulic boundary conditions are obtained from a preceding full-plant MSLB simulation. The assessment of the core safety parameters is supplemented by a fine-mesh (sub-channel) thermal-hydraulic analysis of the hottest assemblies with the CTF code using information from the 3D nodal COBAYA/CTF calculations. Thirteen variants of a pessimistic MSLB scenario are considered, each of them assuming a number of equipment failures aggravated by eight control rods stuck out of the core after scram at different locations in the overcooled sector. The results (within the limitations of the adopted modeling assumptions) show that the core safety parameters do not exceed the safety limits in the simulated aggravated reactivity accidents.

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15

Shiozawa, Ikumi. "Cast Core or Resin Core." Nihon Hotetsu Shika Gakkai Zasshi 47, no. 2 (2003): 253–60. http://dx.doi.org/10.2186/jjps.47.253.

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16

Schultz, Steven. "Common Core or Christian Core?" Catholic Social Science Review 21 (2016): 45–54. http://dx.doi.org/10.5840/cssr2016218.

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17

Shannon, Patrick, Christine Walsh, Jennifer Danridge Turner, Michael Ford, Richard Meyer, Joanne Durham, Mariam Jean Dreher, Rob Simon, and Sharon G. Kane. "Commentaries: Common Core, Rotten Core." Language Arts 91, no. 4 (March 1, 2014): 267–72. http://dx.doi.org/10.58680/la201424590.

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Several readers respond to aspects of CCSS implementation, addressing topics from their sociopolitical context to teacher training to a comparison with Finnish testing practices. Also included are several poetic responses that are sure to evoke a smile or a shudder.

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18

WANG, Lianjie, Wenbo ZHAO, Ping YANG, Yongqiang MA, and Di LU. "ICONE23-1019 DEVELOPMENT AND VERIFICATION OF SNTA CODE SYSTEM FOR SCWR CORE STEADY STATE ANALYSIS." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2015.23 (2015): _ICONE23–1—_ICONE23–1. http://dx.doi.org/10.1299/jsmeicone.2015.23._icone23-1_14.

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19

Dozaki, Koji. "ICONE15-10809 COMPARISON OF DESIGN MARGIN FOR CORE SHROUD IN BETWEEN DESIGN AND CONSTRUCTION CODE AND FITNESS-FOR-SERVICE CODE." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2007.15 (2007): _ICONE1510. http://dx.doi.org/10.1299/jsmeicone.2007.15._icone1510_413.

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20

Wirth, Stephane, Raymond Gauvin, and Ken Kendall. "Experimental Analysis of Core Crushing and Core Movementin RTM and SRIM Foam Cored Composite Parts." Journal of Reinforced Plastics and Composites 17, no. 11 (July 1998): 964–88. http://dx.doi.org/10.1177/073168449801701101.

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21

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 used to analyze the SMR core, in which the lattice calculation was performed by a Monte Carlo code called McCARD with a continuous energy library to generate homogenized two-group assembly cross sections. The SMR core analysis was performed to show neutronic characteristics and TRU mass flow in the SMR core with TRU multi-recycling. The result shows that the analyses on the neutronic characteristics and TRU mass flow using the McCARD/MASTER code system showed good agreement with the previous ones using the DeCART2D/MASTER code system. The neutronic characteristics of each cycle of the core satisfied the typical limit of a commercial PWR core and the SMR core consumes effectively TRU with net TRU consumption rates of 8.46~14.33 %.

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22

Ratna Dewi Syarifah, Nabil Nabhan MH, Zein Hanifah, Iklimatul Karomah, and Ahmad Muzaki Mabruri. "Analisis Fraksi Volume Bahan Bakar Uranium Karbida Pada Reaktor Cepat Berpendingin Gas Menggunakan SRAC Code." Jurnal Jaring SainTek 3, no. 1 (April 28, 2021): 13–18. http://dx.doi.org/10.31599/jaring-saintek.v3i1.333.

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Analysis of fuel volume fraction with uranium caride fuel in Gas Cooled Fast Reactor (GFR) with SRAC Code is has been done. The calculation used SRAC Code (Standard Reactor Analysis Code) which is developed by JAEA (Japan Atomic Energy Agency), and the data libraries nuclear used JENDL 4.0. There are two calculation has been used, fuel pin cell calculation (PIJ Calculation) and core calculation (CITATION Calculation). In core calculation, the leakage is calculated so the calculation more precise. The CITATION calculation use two type of core configuration, i.e. homogeneous core configuration and heterogeneous core configuration. The power density value of two type core configuration is quite difference. It is better use heterogeneous core configuration than homogeneous core configuration, because the power density of heterogeneous core configuration is flatter than the other. From the analysis of fuel volume fraction, when the volume fraction is increase, the k-eff value is increase. And the optimum design after has been analysis for fuel volume fraction, that is the fuel volume fraction is 49% with a heterogeneous core configuration of three types of fuel percentages, for Fuel1 9%, Fuel2 12% and Fuel3 15%. This reactor is cylindrical, has a core diameter of 240 cm and a core height of 100 cm.

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23

Gaillet, Julien, Thomas Bonaccorsi, Gilles Noguere, and Guillaume Truchet. "Development and validation of uncertainty neutron transport calculations at an industrial scale." EPJ Nuclear Sciences & Technologies 4 (2018): 45. http://dx.doi.org/10.1051/epjn/2018031.

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Evaluating uncertainties on nuclear parameters such as reactivity is a major issue for conception of nuclear reactors. These uncertainties mainly come from the lack of knowledge on nuclear and technological data. Today, the common method used to propagate nuclear data uncertainties is Total Monte Carlo [1] but this method suffers from a long time calculation. Moreover, it requires as many calculations as uncertainties sought. An other method for the propagation of the nuclear data uncertainties consists in using the standard perturbation theory (SPT) to calculate reactivity sensitivity to the desire nuclear data. In such a method, sensitivities are combined with a priori nuclear data covariance matrices such as the COMAC set developed by CEA. The goal of this work is to calculate sensitivites by SPT with the full core diffusion code CRONOS2 for propagation uncertainties at the core level. In this study, COMAC nuclear data uncertainties have been propagated on the BEAVRS benchmark using a two-step APOLLO2/CRONOS2 scheme, where APOLLO2 is the lattice code used to resolve Boltzmann equation within assemblies using a high number of energy groups, and CRONOS2 is the code resolving the 3D full core diffusion equation using only four energy groups. A module implementing the SPT already exists in the APOLLO2 code but computational cost would be too expensive in 3D on the whole core. Consequently, an equivalent procedure has been created in CRONOS2 code to allow full-core uncertainty propagation. The main interest of this procedure is to compute sensitivities on reactivity within a reduced turnaround time for a 3D modeled core, even after fuel depletion. In addition, it allows access to all sensitivites by isotope, reaction and energy group in a single calculation. Reactivity sensitivities calculated by this procedure with four energy groups are compared to reference sensitivities calculated by the iterated fission probability (IFP) method in Monte Carlo code. For the purpose of the tests, dedicated covariance matrix have been created by condensation from 49 to 4 groups of the COMAC matrix. In conclusion, sensitivities calculated by CRONOS2 agree with the sensitivities calculated by the IFP method, which validates the calculation procedure, allowing analysis to be done quickly. In addition, reactivity uncertainty calculated by this method is close to values found for this type of reactor.

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24

Bucchi, Marco, Alejandro Grez, Andrés Quintana, Cristian Riveros, and Stijn Vansummeren. "CORE." Proceedings of the VLDB Endowment 15, no. 9 (May 2022): 1951–64. http://dx.doi.org/10.14778/3538598.3538615.

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Complex Event Recognition (CER) systems are a prominent technology for finding user-defined query patterns over large data streams in real time. CER query evaluation is known to be computationally challenging, since it requires maintaining a set of partial matches, and this set quickly grows super-linearly in the number of processed events. We present CORE, a novel COmplex event Recognition Engine that focuses on the efficient evaluation of a large class of complex event queries, including time windows as well as the partition-by event correlation operator. This engine uses a novel automaton-based evaluation algorithm that circumvents the super-linear partial match problem: under data complexity, it takes constant time per input event to maintain a data structure that compactly represents the set of partial matches and, once a match is found, the query results may be enumerated from the data structure with output-linear delay. We experimentally compare CORE against state-of-the-art CER systems on real-world data. We show that (1) CORE's performance is stable with respect to both query and time window size, and (2) CORE outperforms the other systems by up to five orders of magnitude on different workloads.

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25

Rosenblum, Sophie. "Core, Mantle, Crust, Crust, Mantle, Core." Iowa Review 41, no. 2 (October 2011): 183. http://dx.doi.org/10.17077/0021-065x.7043.

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26

Parker, S. H. "When is core biopsy really core?" Radiology 185, no. 3 (December 1992): 641–42. http://dx.doi.org/10.1148/radiology.185.3.1438739.

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27

Liemohn, W. P., R. C. Johnson, J. C. Sanders, and J. Woods. "MEASURING CORE STRENGTH AND CORE STABILITY." Medicine & Science in Sports & Exercise 34, no. 5 (May 2002): S153. http://dx.doi.org/10.1097/00005768-200205001-00853.

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28

ZANDER, KAREN. "The 1990s: Core Values, Core Change." Frontiers of Health Services Management 7, no. 2 (1990): 28–32. http://dx.doi.org/10.1097/01974520-199010000-00005.

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29

Liu, Xuesong, Zhongwei Fan, Zhaohui Shi, Yunfeng Ma, Jin Yu, and Jing Zhang. "Dual-core antiresonant hollow core fibers." Optics Express 24, no. 15 (July 22, 2016): 17453. http://dx.doi.org/10.1364/oe.24.017453.

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30

Pettersson, Lars G. M. "Large atomic core—core correlation effects." Chemical Physics Letters 180, no. 4 (May 1991): 365–68. http://dx.doi.org/10.1016/0009-2614(91)90335-7.

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31

Gramain, Jean-Baptiste, and Rishi Nath. "On core and bar-core partitions." Ramanujan Journal 27, no. 2 (August 20, 2011): 229–33. http://dx.doi.org/10.1007/s11139-011-9309-y.

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32

Silin, Silin M. V., Alexander V. Levchenko, and Grigorieva O. A. Grigorieva. "Verification of DYNCO code in HTGR core simulating." Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika 2013, no. 3 (May 2013): 62–69. http://dx.doi.org/10.26583/npe.2013.3.08.

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33

Tam, Bit Shun, and Hans Schneider. "On the core of a cone-preserving map." Transactions of the American Mathematical Society 343, no. 2 (February 1, 1994): 479–524. http://dx.doi.org/10.1090/s0002-9947-1994-1242787-6.

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34

Mocák, Miroslav, Ewald Müller, Achim Weiss, and Konstantinos Kifonidis. "Hydrodynamic simulations of the core helium flash." Proceedings of the International Astronomical Union 4, S252 (April 2008): 215–21. http://dx.doi.org/10.1017/s1743921308022813.

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AbstractWe desribe and discuss hydrodynamic simulations of the core helium flash using an initial model of a 1.25 M⊙ star with a metallicity of 0.02 near at its peak. Past research concerned with the dynamics of the core helium flash is inconclusive. Its results range from a confirmation of the standard picture, where the star remains in hydrostatic equilibrium during the flash (Deupree 1996), to a disruption or a significant mass loss of the star (Edwards 1969; Cole & Deupree 1980). However, the most recent multidimensional hydrodynamic study (Dearborn et al. 2006) suggests a quiescent behavior of the core helium flash and seems to rule out an explosive scenario. Here we present partial results of a new comprehensive study of the core helium flash, which seem to confirm this qualitative behavior and give a better insight into operation of the convection zone powered by helium burning during the flash. The hydrodynamic evolution is followed on a computational grid in spherical coordinates using our new version of the multi-dimensional hydrodynamic code HERAKLES, which is based on a direct Eulerian implementation of the piecewise parabolic method.

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35

Zhou, Yuancheng, Yunzhao Li, Ruizhi Shao, Sicheng Wang, and Yisong Li. "Automatic modeling of PWR-core in the two-step reactor-core physics analysis code NECP-Bamboo." Nuclear Engineering and Design 414 (December 2023): 112546. http://dx.doi.org/10.1016/j.nucengdes.2023.112546.

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36

Waltz, J., J. G. Wohlbier, L. D. Risinger, T. R. Canfield, M. R. J. Charest, A. R. Long, and N. R. Morgan. "Performance analysis of a 3D unstructured mesh hydrodynamics code on multi-core and many-core architectures." International Journal for Numerical Methods in Fluids 77, no. 6 (November 27, 2014): 319–33. http://dx.doi.org/10.1002/fld.3982.

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37

Tollit, Brendan, Alan Charles, William Poole, Andrew Cox, Glynn Hosking, Ben Lindley, Peter Smith, Andy Smethurst, and Jean Lavarenne. "WHOLE CORE COUPLING METHODOLOGIES WITHIN WIMS." EPJ Web of Conferences 247 (2021): 06006. http://dx.doi.org/10.1051/epjconf/202124706006.

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The ANSWERS® WIMS reactor physics code is being developed for whole core multiphysics modelling. The established neutronics capability for lattice calculations has recently been extended to be suitable for whole core modelling of Small Modular Reactors (SMRs). A whole core transport, SP3 or diffusion flux solution is combined with fuel assembly resonance shielding and pin-by-pin differential depletion. An integrated thermal hydraulic solver permits differential temperature and density variations to feedback to the neutronics calculation. This paper presents new methodology developed in WIMS to couple the core neutronics to the integrated core thermal hydraulics solver. Two coupling routes are presented and compared using a challenging PWR SMR benchmark. The first route, called GEOM, dynamically calculates the resonance shielding and homogenisation with the whole core flux solution. The second coupling route, called CAMELOT, separates the resonance shielding and pincell homogenisation from the whole core solution via generating tabulated cross sections. Both routes can use the MERLIN homogenised pin-by-pin whole core flux solver and couple to the same integrated thermal hydraulic solver, called ARTHUR. Heterogeneous differences between the neutronics and thermal hydraulics are mapped via thermal identifiers for neutronics materials and thermal regions. The ability for the integrated thermal hydraulic solver to call an external code via a Fortran-C-Python (FCP) interface is also summarised. This flexible external coupling permits one way coupling to an external fuel performance code or two way coupling to an external thermal hydraulic code.

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Qiao, G. J., J. F. Liu, Yang Wang, X. J. Wu, and J. L. Han. "Hollow Core?" International Astronomical Union Colloquium 177 (2000): 197–98. http://dx.doi.org/10.1017/s0252921100059455.

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AbstractWe carried out the Gaussian fitting to the profile of PSR B1237+25 and found that six components rather than five are necessary to make a good fit. In the central part, we found that the core emission is not filled pencil beam but is a small hollow cone. This implies that the impact angle could beβ< 0.5°. The “hollow core” is in agreement with Inverse Compton Scattering model of radio pulsars.

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Luthfi, Wahid, and Surian Pinem. "VALIDATION OF SRAC CODE SYSTEM FOR NEUTRONIC PARAMETERS CALCULATION OF THE PWR MOX/UO2 CORE BENCHMARK." Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir 27, no. 1 (February 28, 2021): 47. http://dx.doi.org/10.17146/urania.2021.27.1.6238.

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VALIDATION OF SRAC CODE SYSTEM FOR NEUTRONIC PARAMETERS CALCULATION OF THE PWR MOX/UO2 CORE BENCHMARK. Determination of neutronic parameter value is an important part in determining reactor safety, so accurate calculation results can be obtained. This study is focused on the validation of SRAC code system in the calculation of neutronic parameters value of a PWR (Pressurized Water Reactor) reactor core. MOX/UO2 Core Benchmark was choosed because it is used by several researchers as a reference core for code validation in the determination of neutronic parameters of a reactor core. The neutronic parameters calculated include critical boron concentration, delayed neutron fraction, and Power Peaking Factor (PPF) and its distribution in axial and radial directions. When compared with reference data, the calculation results of the critical boron concentration value show that there is a difference of 22.5 ppm on SRAC code system. Meanwhile, differences in power per fuel element (assembly power error) value of power-weighted error (PWE) and error-weighted error (EWE) is 2.93% and 3.94%, respectively. Maximum difference between PPF value in axial direction with reference reaches a value of 4.57%. SRAC calculation results also show consistency with the calculation results of other program packages or code. Results of this study indicate that SRAC code system is still quite accurate for the calculation of neutronic parameters of PWR reactor core benchmark. Therefore, SRAC code system can be used to calculate neutronic parameters of PWR reactor core, especially when using MOX (mixed oxide) fuel.Keywords: Neutronic parameter, critical boron concentration, power peaking factor, SRAC code system.

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Wagenaar, Theodore C. "Core as Science or Core as Major? Impediments to Identifying the Core." Teaching Sociology 32, no. 1 (January 2004): 37–38. http://dx.doi.org/10.1177/0092055x0403200103.

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Li, Shan Hong, Li Jun Li, De Ren Li, and Zhi Chao Lu. "Core Losses Separation of Amorphous Alloy Core." Materials Science Forum 849 (March 2016): 91–94. http://dx.doi.org/10.4028/www.scientific.net/msf.849.91.

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In this paper, the core losses of Fe80Si9B11, Fe78Si9B13 amorphous alloy cores were separated to investigate the behaviors of hysteresis loss, eddy current loss and additional loss in high frequency range. The results showed that the losses of amorphous alloy core were mainly composed of hysteresis loss in low frequency. With the increase of frequency, eddy current loss increased drastically compared with the hysteresis loss, the eddy current loss was greater than the hysteresis loss when the frequency was higher than 5 kHz and 6 kHz for amorphous alloy with the composition of Fe78Si9B13 and Fe80Si9B11, respectively. The eddy current loss proportion in total loss increased with the increment of frequency.

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Olney, Marjorie F., and Kenneth J. Gill. "Can Psychiatric Rehabilitation Be Core to CORE?" Rehabilitation Research, Policy, and Education 30, no. 3 (2016): 204–14. http://dx.doi.org/10.1891/2168-6653.30.3.204.

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Purpose: In this article, we seek to determine whether psychiatric rehabilitation principles and practices have been more fully incorporated into the Council on Rehabilitation Education (CORE) standards, the extent to which they are covered in four rehabilitation counseling “foundations” textbooks, and how they are reflected in the contents of three key journals in rehabilitation counseling.Methods: We conducted a detailed review of literature that has surveyed coordinators of graduate programs accredited by the CORE as well as research that investigates the preparedness of graduates of CORE-accredited rehabilitation counseling programs to deliver services to people with psychiatric disabilities.Results: This review found that psychiatric rehabilitation is only touched upon in the CORE standards, is modestly alluded to in the most commonly used foundational textbooks, and has very few articles about it published annually in rehabilitation journals.Conclusion: Recommendations on methods for increasing psychiatric rehabilitation content in CORE-accredited programs are provided. Specific suggestions are made for resources and activities that can be added to rehabilitation counseling curricula to include psychiatric rehabilitation.

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Horčic, M., J. Svoboda, V. Novotná, D. Pociecha, and E. Gorecka. "Core-to-core dimers forming switchable mesophase." Chemical Communications 53, no. 18 (2017): 2721–24. http://dx.doi.org/10.1039/c6cc09983a.

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Sánchez-Rodríguez, E., P. Borm, A. Estévez-Fernández, M. G. Fiestras-Janeiro, and M. A. Mosquera. "$$k$$ k -core covers and the core." Mathematical Methods of Operations Research 81, no. 2 (January 1, 2015): 147–67. http://dx.doi.org/10.1007/s00186-014-0490-9.

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Fayers, Matthew. "The t-core of an s-core." Journal of Combinatorial Theory, Series A 118, no. 5 (July 2011): 1525–39. http://dx.doi.org/10.1016/j.jcta.2011.01.004.

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Pitzer, Russell M., and Nicholas W. Winter. "Spin-orbit (core) and core potential integrals." International Journal of Quantum Chemistry 40, no. 6 (December 1991): 773–80. http://dx.doi.org/10.1002/qua.560400606.

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Jaakko, Miettinen, Raty Hanna, and Daavittila Antti. "ICONE15-10292 THE 3D CORE THERMOHYDRAULICS AND NEUTRONICS SOLUTION IN THE TRAB-SMABRE ACCIDENT AND TRANSIENT CODE." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2007.15 (2007): _ICONE1510. http://dx.doi.org/10.1299/jsmeicone.2007.15._icone1510_147.

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Svitalsky, Marcel. "The Dublin Core Metadata Interface Project." Zpravodaj Československého sdružení uživatelů TeXu 19, no. 1-2 (2009): 102–6. http://dx.doi.org/10.5300/2009-1-2/102.

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Yang, Wen, Hongchun Wu, Yunzhao Li, Jiewei Yang, and Liangzhi Cao. "Development and verification of PWR-core fuel management calculation code system NECP-Bamboo: Part II Bamboo-Core." Nuclear Engineering and Design 337 (October 2018): 279–90. http://dx.doi.org/10.1016/j.nucengdes.2018.07.017.

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Yu, Hwanyeal, Hyunsik Hong, and Jooil Yoon. "Analysis of the APR1400 Benchmark Using High-Fidelity Pin-Wise Core Calculation Codes." Energies 17, no. 14 (July 17, 2024): 3498. http://dx.doi.org/10.3390/en17143498.

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The KEPCO Nuclear Fuel Company (KNF) has undertaken considerable efforts to improve the KARMA/ASTRA nuclear design code system to meet the increasing demand for high-fidelity core analyses. Through years of effort, the KARMA lattice transport code based on the method of characteristics (MOC) has evolved into KARMA2, a direct whole core calculation code using a 3D calculation method based on planar (2D) MOC principles. Simultaneously, ASTRA2, designed as the successor to the ASTRA nodal diffusion code, has been developed. ASTRA2 exhibits enhanced capabilities in multigroup pin-by-pin core calculations, achieved by decoupling the 3D whole core problem into a series of planar and axial problems. The domain size of each axial problem can be adjusted, ranging from pin-cell to assembly scale, thereby optimizing efficiency. The verification and validation process of the KARMA2/ASTRA2 code system involves various benchmark problems and measured data from operational PWRs. In this study, the APR1400 benchmark analysis was performed to verify the neutronics calculation capabilities of both codes. The results underscore the reliability and accuracy of the KARMA2 solutions across various core conditions, exhibiting close agreement with the McCARD reference solutions. Similarly, the ASTRA2 results agree with the corresponding KARMA2 results. These successful results demonstrate the high-fidelity core calculation capabilities of KNF’s next-generation code system.

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