1
|
Hugo Sanchez-Espinoza V, Zhang K, Campos Muñoz A, Böttcher M. KIT Multi-scale thermal–hydraulic coupling methods for improved simulation of nuclear power plants. NUCLEAR ENGINEERING AND DESIGN 2023. [DOI: 10.1016/j.nucengdes.2023.112218] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 02/27/2023]
|
2
|
Investigation on Safety Dynamic Evolution Mechanism of a Distributed Low Carbon Manufacturing System with Large Time Delay. Processes (Basel) 2022. [DOI: 10.3390/pr10091707] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/17/2022] Open
Abstract
In order to reveal the inducing factors and safety dynamic evolution mechanism of frequent personal injury accidents under a low carbon manufacturing process, a nonlinear safety dynamic evolution model of a distributed low carbon manufacturing system with large time delay is established. The established model is then verified by simulation results from mathematical analysis and dynamic evolution. Moreover, qualitative analysis on nonlinear safety dynamic evolution and the trend of human–machine safety under a low carbon manufacturing process is investigated. Finally, an application case of the established model is studied. The key results are as follows: (1) There are four dynamic regions, namely the safety area I, the deterioration area II, the asymptotically stable safety area III, and the enhancement area IV of the safety ability in the interaction evolution model of carelessness and safety levels; (2) There are two singularities in the dynamic evolution model of the man–machine safety system with large time delay under a low carbon manufacturing process; (3) The equilibrium points of the human–machine safety system are El = (0, 0) and E2 = (0.5333, 0.2489), while changes in the carelessness level have a serious block effect on safety development with time; (4) For the radial tire casing process, the low carbon development trend of the technological process of radial tire casing is good, but low carbon structure and management have slightly lower low carbon levels. This work provides a theoretical basis for the safety evaluation and control of the distributed low carbon manufacturing human–machine safety system with large time delay.
Collapse
|
3
|
Wang J, Wang Q, Ding M. Review on neutronic/thermal-hydraulic coupling simulation methods for nuclear reactor analysis. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2019.107165] [Citation(s) in RCA: 18] [Impact Index Per Article: 4.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
|
4
|
Liao Y, Krepper E, Lucas D. A baseline closure concept for simulating bubbly flow with phase change: A mechanistic model for interphase heat transfer coefficient. NUCLEAR ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.nucengdes.2019.04.007] [Citation(s) in RCA: 9] [Impact Index Per Article: 1.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
|
5
|
Jeltsov M, Grishchenko D, Kudinov P. Validation of Star-CCM+ for liquid metal thermal-hydraulics using TALL-3D experiment. NUCLEAR ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.nucengdes.2018.11.015] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
|
6
|
Introini C, Lorenzi S, Cammi A, Baroli D, Peters B, Bordas S. A Mass Conservative Kalman Filter Algorithm for Computational Thermo-Fluid Dynamics. MATERIALS (BASEL, SWITZERLAND) 2018; 11:E2222. [PMID: 30413109 PMCID: PMC6267179 DOI: 10.3390/ma11112222] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Abstract] [Key Words] [Grants] [Track Full Text] [Download PDF] [Figures] [Subscribe] [Scholar Register] [Received: 10/11/2018] [Revised: 10/26/2018] [Accepted: 10/30/2018] [Indexed: 11/16/2022]
Abstract
This paper studies Kalman filtering applied to Reynolds-Averaged Navier⁻Stokes (RANS) equations for turbulent flow. The integration of the Kalman estimator is extended to an implicit segregated method and to the thermodynamic analysis of turbulent flow, adding a sub-stepping procedure that ensures mass conservation at each time step and the compatibility among the unknowns involved. The accuracy of the algorithm is verified with respect to the heated lid-driven cavity benchmark, incorporating also temperature observations, comparing the augmented prediction of the Kalman filter with the Computational Fluid-Dynamic solution found on a fine grid.
Collapse
Affiliation(s)
- Carolina Introini
- Politecnico di Milano, Department of Energy, via La Masa 34, I-20156 Milano, Italy.
| | - Stefano Lorenzi
- Politecnico di Milano, Department of Energy, via La Masa 34, I-20156 Milano, Italy.
| | - Antonio Cammi
- Politecnico di Milano, Department of Energy, via La Masa 34, I-20156 Milano, Italy.
| | - Davide Baroli
- Department of Computational Engineering Sciences, Faculty of Science, Engineering and Communication, University of Luxembourg, 6 Avenue de la Fonte, 4364 Esch-sur-Alzette, Luxembourg.
| | - Bernhard Peters
- Department of Computational Engineering Sciences, Faculty of Science, Engineering and Communication, University of Luxembourg, 6 Avenue de la Fonte, 4364 Esch-sur-Alzette, Luxembourg.
| | - Stéphane Bordas
- Department of Computational Engineering Sciences, Faculty of Science, Engineering and Communication, University of Luxembourg, 6 Avenue de la Fonte, 4364 Esch-sur-Alzette, Luxembourg.
- School of Engineering, Cardiff University, Queen's Building, The Parade, Cardiff CF24 3AA, Wales, UK.
- Department of Medical Research, China Medical University Hospital, China Medical University, Taichung 40402, Taiwan.
| |
Collapse
|
7
|
Eulerian modelling of turbulent bubbly flow based on a baseline closure concept. NUCLEAR ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.nucengdes.2018.07.021] [Citation(s) in RCA: 33] [Impact Index Per Article: 5.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
|
8
|
Henry R, Tiselj I, Snoj L. Transient CFD/Monte-Carlo Neutron Transport Coupling Scheme for simulation of a control rod extraction in TRIGA reactor. NUCLEAR ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.nucengdes.2018.03.015] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
|
9
|
Henry R, Tiselj I, Snoj L. CFD/Monte-Carlo neutron transport coupling scheme, application to TRIGA reactor. ANN NUCL ENERGY 2017. [DOI: 10.1016/j.anucene.2017.06.018] [Citation(s) in RCA: 17] [Impact Index Per Article: 2.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
|
10
|
Smith BL. On the Establishment of a Web Portal for the Assessment of CFD in Reactor Safety Analysis. NUCL TECHNOL 2017. [DOI: 10.13182/nt11-a12514] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Affiliation(s)
- Brian L. Smith
- Paul Scherrer Institute, Thermal Hydraulics Laboratory Nuclear Energy and Safety Department, CH-5232 Villigen PSI, Switzerland
| |
Collapse
|
11
|
Saeed M, Yu J, Abdalla AAA, Hou B, Hussain G, Zhong X. The effect of turbulence modeling on hydrogen jet dispersion inside a compartment space using the HYDRAGON code. J NUCL SCI TECHNOL 2017. [DOI: 10.1080/00223131.2017.1299645] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
Affiliation(s)
- Muhammad Saeed
- Department of Engineering Physics, Tsinghua University, Beijing, China
| | - Jiyang Yu
- Department of Engineering Physics, Tsinghua University, Beijing, China
| | | | - Bingxu Hou
- Department of Engineering Physics, Tsinghua University, Beijing, China
| | - Ghulam Hussain
- Department of Engineering Physics, Tsinghua University, Beijing, China
| | - Xianping Zhong
- Department of Engineering Physics, Tsinghua University, Beijing, China
| |
Collapse
|
12
|
Sun L, Peng M, Xia G, Lv X, Li R. Numerical Study on Coolant Flow Distribution at the Core Inlet for an Integral Pressurized Water Reactor. NUCLEAR ENGINEERING AND TECHNOLOGY 2017. [DOI: 10.1016/j.net.2016.07.005] [Citation(s) in RCA: 12] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
|
13
|
Shams A, Damiani G, Rosa D, Komen E. Design of a single-phase PTS numerical experiment for a reference Direct Numerical Simulation. NUCLEAR ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.nucengdes.2016.01.038] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
|
14
|
Bucalossi A, Moretti F, Melideo D, Del Nevo A, D’Auria F, Höhne T, Lisenkov E, Gallori D. Experimental investigation of in-vessel mixing phenomena in a VVER-1000 scaled test facility during unsteady asymmetric transients. NUCLEAR ENGINEERING AND DESIGN 2011. [DOI: 10.1016/j.nucengdes.2011.05.005] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
|
15
|
Loginov M, Komen E, Höhne T. Application of large-eddy simulation to pressurized thermal shock: Assessment of the accuracy. NUCLEAR ENGINEERING AND DESIGN 2011. [DOI: 10.1016/j.nucengdes.2011.05.027] [Citation(s) in RCA: 11] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
|
16
|
|
17
|
Jamet D, Lebaigue O, Morel C, Arcen B. Towards a multi-scale approach of two-phase flow modeling in the context of DNB modeling. NUCLEAR ENGINEERING AND DESIGN 2010. [DOI: 10.1016/j.nucengdes.2009.11.034] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
|
18
|
Smith BL. ASSESSMENT OF CFD CODES USED IN NUCLEAR REACTOR SAFETY SIMULATIONS. NUCLEAR ENGINEERING AND TECHNOLOGY 2010. [DOI: 10.5516/net.2010.42.4.339] [Citation(s) in RCA: 24] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
|
19
|
Jeong JJ, Yoon HY, Park IK, Cho HK, Lee HD. DEVELOPMENT AND PRELIMINARY ASSESSMENT OF A THREE-DIMENSIONAL THERMAL HYDRAULICS CODE, CUPID. NUCLEAR ENGINEERING AND TECHNOLOGY 2010. [DOI: 10.5516/net.2010.42.3.279] [Citation(s) in RCA: 31] [Impact Index Per Article: 2.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
|
20
|
Implementation of a second-order upwind method in a semi-implicit two-phase flow code on unstructured meshes. ANN NUCL ENERGY 2010. [DOI: 10.1016/j.anucene.2009.12.015] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
|
21
|
Khane V, Usman S. Further on integrator circuit analogy for natural convection. NUCLEAR ENGINEERING AND DESIGN 2010. [DOI: 10.1016/j.nucengdes.2009.10.007] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
|
22
|
Paladino D, Zboray R, Benz P, Andreani M. Three-gas mixture plume inducing mixing and stratification in a multi-compartment containment. NUCLEAR ENGINEERING AND DESIGN 2010. [DOI: 10.1016/j.nucengdes.2008.07.014] [Citation(s) in RCA: 23] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
|
23
|
Štrubelj L, Ézsöl G, Tiselj I. Direct contact condensation induced transition from stratified to slug flow. NUCLEAR ENGINEERING AND DESIGN 2010. [DOI: 10.1016/j.nucengdes.2008.12.004] [Citation(s) in RCA: 26] [Impact Index Per Article: 1.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
|
24
|
de la Rosa J, Escrivá A, Herranz L, Cicero T, Muñoz-Cobo J. Review on condensation on the containment structures. PROGRESS IN NUCLEAR ENERGY 2009. [DOI: 10.1016/j.pnucene.2008.01.003] [Citation(s) in RCA: 88] [Impact Index Per Article: 5.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
|
25
|
A semi-implicit numerical scheme for transient two-phase flows on unstructured grids. NUCLEAR ENGINEERING AND DESIGN 2008. [DOI: 10.1016/j.nucengdes.2008.08.017] [Citation(s) in RCA: 18] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
|
26
|
Yadigaroglu G, Simiano M, Milenkovic R, Kubasch J, Milelli M, Zboray R, De Cachard F, Smith B, Lakehal D, Sigg B. CFD4NRS with a focus on experimental and CMFD investigations of bubbly flows. NUCLEAR ENGINEERING AND DESIGN 2008. [DOI: 10.1016/j.nucengdes.2007.02.047] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
|
27
|
CFD simulation of the Vattenfall 1/5th-scale PWR model for boron dilution studies. NUCLEAR ENGINEERING AND DESIGN 2008. [DOI: 10.1016/j.nucengdes.2007.02.038] [Citation(s) in RCA: 9] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
|
28
|
CFD simulations of light gas release and mixing in the Battelle Model-Containment with CFX. NUCLEAR ENGINEERING AND DESIGN 2008. [DOI: 10.1016/j.nucengdes.2007.02.042] [Citation(s) in RCA: 17] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
|
29
|
Andreani M, Haller K, Heitsch M, Hemström B, Karppinen I, Macek J, Schmid J, Paillere H, Toth I. A benchmark exercise on the use of CFD codes for containment issues using best practice guidelines: A computational challenge. NUCLEAR ENGINEERING AND DESIGN 2008. [DOI: 10.1016/j.nucengdes.2007.01.021] [Citation(s) in RCA: 24] [Impact Index Per Article: 1.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/15/2022]
|
30
|
Smith BL. A numerical investigation of three-dimensional flows in large volumes in the context of passive containment cooling in BWRs. NUCLEAR ENGINEERING AND DESIGN 2007. [DOI: 10.1016/j.nucengdes.2007.02.001] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
|