4.5 Article

Fluid-to-fluid scaling of heat transfer phenomena with supercritical pressure fluids: Results from RANS analyses

期刊

ANNALS OF NUCLEAR ENERGY
卷 92, 期 -, 页码 21-35

出版社

PERGAMON-ELSEVIER SCIENCE LTD
DOI: 10.1016/j.anucene.2016.01.028

关键词

Supercritical pressure; CFD; Deteriorated heat transfer; Fluid-to-fluid scaling

资金

  1. IAEA [18425/R0]

向作者/读者索取更多资源

A methodology for fluid-to-fluid scaling of predicted heat transfer phenomena with supercritical pressure fluids is being developed with the aid of RANS calculations. The proposed approach rephrases and further develops a previous attempt, whose preliminary validation was limited by the considerable inaccuracy of the adopted turbulence models when applied to deteriorated heat transfer. A recent improvement in the accuracy of heat transfer predictions allowed this further step, also based on the broader experience gained in the mean time in the prediction of experimental data. Four representative experimental data cases related to water and CO2, for which reasonably accurate results have been obtained by RANS turbulence equations, are addressed by changing the working fluid and imposing an approximate invariance of the dimensionless trends of fluid enthalpy at the wall and in bulk. Intrinsic differences in the thermal behaviour of the considered fluids (e.g., in the Prandtl number) are reflected in corresponding changes in the value of a single dimensionless parameter, following an indication coming from simple theoretical considerations. Results of RANS models for different fluids are used as a preliminary support to the validity of the approach, showing an interesting persistence of heat transfer behaviour in dimensionless form in the four addressed cases. The present uncertainties in the proposed methodology are mainly a consequence of the limited accuracy of the adopted simulation models. The obtained indications can be used in planning experimental or better resolved computational analyses (LES, DNS) which may better clarify the promising features of this approach. (C) 2016 Elsevier Ltd. All rights reserved.

作者

我是这篇论文的作者
点击您的名字以认领此论文并将其添加到您的个人资料中。

评论

主要评分

4.5
评分不足

次要评分

新颖性
-
重要性
-
科学严谨性
-
评价这篇论文

推荐

Article Nuclear Science & Technology

Simulation of operational conditions of HX-HERO in the CIRCE facility with CFD/STH coupled codes

F. Galleni, G. Barone, D. Martelli, A. Pucciarelli, P. Lorusso, M. Tarantino, N. Forgione

NUCLEAR ENGINEERING AND DESIGN (2020)

Article Nuclear Science & Technology

Analysis of thermal stratification phenomena in the CIRCE-HERO facility

F. Buzzi, A. Pucciarelli, F. Galleni, M. Tarantino, N. Forgione

ANNALS OF NUCLEAR ENERGY (2020)

Article Thermodynamics

A successful local fluid-to-fluid similarity theory for heat transfer to supercritical pressure fluids: merits and limitations

Andrea Pucciarelli, Shuisheng He, Walter Ambrosini

INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER (2020)

Article Thermodynamics

A successful general fluid-to-fluid similarity theory for heat transfer at supercritical pressure

Andrea Pucciarelli, Walter Ambrosini

INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER (2020)

Article Chemistry, Multidisciplinary

STH/CFD Coupled Simulation of the Protected Loss of Flow Accident in the CIRCE-HERO Facility

Pucciarelli Andrea, Galleni Francesco, Moscardini Marigrazia, Martelli Daniele, Forgione Nicola

APPLIED SCIENCES-BASEL (2020)

Article Chemistry, Multidisciplinary

Numerical Analysis of the CIRCE-HERO PLOFA Scenarios

Moscardini Marigrazia, Galleni Francesco, Pucciarelli Andrea, Martelli Daniele, Forgione Nicola

APPLIED SCIENCES-BASEL (2020)

Article Nuclear Science & Technology

STH/CFD coupled calculations of postulated transients from mixed to natural circulation conditions in the NACIE-UP facility

A. Pucciarelli, F. Galleni, M. Moscardini, D. Martelli, N. Forgione

NUCLEAR ENGINEERING AND DESIGN (2020)

Article Nuclear Science & Technology

Coupled system thermal Hydraulics/CFD models: General guidelines and applications to heavy liquid metals

A. Pucciarelli, A. Toti, D. Castelliti, F. Belloni, K. Van Tichelen, M. Moscardini, F. Galleni, N. Forgione

Summary: This article reviews the general guidelines for conducting coupled System Thermal Hydraulics (STH)/CFD calculations, discussing the necessity and advantages of coupled analysis, analyzing different coupling methods and application fields, and summarizing a set of good practice guidelines.

ANNALS OF NUCLEAR ENERGY (2021)

Article Thermodynamics

Insight into a fluid-to-fluid similarity theory for heat transfer at supercritical pressure: Results and perspectives

Sara Kassem, Andrea Pucciarelli, Walter Ambrosini

Summary: The study establishes a similarity theory for heat transfer at supercritical pressures, solving the problem of finding similar behavior between different fluids using original definitions. Further evidence from numerical simulations supports the theory's choices and comparisons of four different fluids under varying conditions.

INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER (2021)

Article Energy & Fuels

Overview of a Theory for Planning Similar Experiments with Different Fluids at Supercritical Pressure

Andrea Pucciarelli, Sara Kassem, Walter Ambrosini

Summary: Recent advancements in the development of a fluid-to-fluid similarity theory for heat transfer with fluids at supercritical pressures are summarized, with a focus on the application in Supercritical Water nuclear Reactors. The developed rationale, based on a specific definition of similarity, aims to achieve similar distributions of enthalpies and fluid densities in a duct containing fluids at supercritical pressure, providing assurance for representing complex heat transfer phenomena. The theory can be used for planning experiments and setting up correlations for heat transfer in different regimes, enhancing our understanding and predictive capabilities in this challenging area.

ENERGIES (2021)

Article Nuclear Science & Technology

Thermo-hydraulic analysis of PbLi ancillary system of WCLL TBM undergoing in-box LOCA

M. Moscardini, F. Galleni, A. Pucciarelli, M. Eboli, A. Del Nevo, S. Paci, N. Forgione

Summary: The study aims to develop a numerical model to simulate the thermo-hydraulic behavior of the PbLi ancillary system under normal operation and accidental scenarios, investigating the propagation of pressure waves resulting from an in-box LOCA.

FUSION ENGINEERING AND DESIGN (2021)

Article Energy & Fuels

Numerical Simulation of an Out-Vessel Loss of Coolant from the Breeder Primary Loop Due to Large Rupture of Tubes in a Primary Heat Exchanger in the DEMO WCLL Concept

Francesco Galleni, Marigrazia Moscardini, Andrea Pucciarelli, Maria Teresa Porfiri, Nicola Forgione

Summary: This work presents a thermohydraulic analysis of a postulated accident involving the rupture of the breeder primary cooling loop inside a heat exchanger. The results show that the pressures and temperatures inside the whole system remain below the safety thresholds for the whole transient, demonstrating effective control of the system throughout the entire transition.

ENERGIES (2021)

Article Thermodynamics

Study of fluid-to-fluid scaling for upward pipe flows of supercritical fluids using direct numerical simulation

Jundi He, Wei Wang, Junjie Yan, Andrea Pucciarelli, Peixue Jiang, Walter Ambrosini, Shuisheng He

Summary: Fluid-to-fluid scaling is a widely applied method in experiments of supercritical fluid flows to reduce cost and technical difficulties. In this study, direct numerical simulations are used to assess a scaling scheme and establish further understanding of the conditions and parameters that determine the similarity in upward heated flows of supercritical fluids.

INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER (2022)

Article Nuclear Science & Technology

Numerical prediction of turbulent flow and heat transfer in buoyancy-affected liquid metal flows

Andrea Pucciarelli, Afaque Shams, Nicola Forgione

Summary: The present paper investigates the capabilities of selected RANS turbulence models in reproducing DNS data for liquid metals thermal hydraulics. Forced and mixed convection conditions, addressing buoyancy-aided and buoyancy-opposed flow, are considered. The paper focuses on velocity and temperature fields estimation, comparing RANS and DNS computations. The results show that the AHFM model provides better predictions for the phenomena considered, particularly for temperature fields, supporting its use as a valuable tool for predicting turbulent heat fluxes.

ANNALS OF NUCLEAR ENERGY (2023)

Article Nuclear Science & Technology

CFD prediction of heat transfer at supercritical pressure with rough walls: Parametric analyses and comparison with experimental data

S. Kassem, A. Pucciarelli, W. Ambrosini

Summary: In this paper, the authors use a low-Reynolds number turbulence model to predict heat transfer at supercritical pressure with different degrees of surface finishing. The model is able to reproduce friction factors and is based on a simple description of the effect of wall protrusions on turbulence production in the boundary layer. Sensitivity analysis is conducted to characterize the predictions at different roughness parameter values, especially with respect to the possibility of suppressing deteriorated heat transfer by roughened surfaces. Experimental data on carbon dioxide are used to validate the model's capability to predict wall temperature values with different boundary conditions. The described model shows promise not only in predicting experimentally measured effects, but also in studying the behavior of purposely roughened surfaces to reduce the occurrence of deteriorated heat transfer.

ANNALS OF NUCLEAR ENERGY (2023)

Article Nuclear Science & Technology

Numerical simulation of tritium extraction from liquid PbLi by gas-liquid contactor

Kecheng Jiang, Jinzhao Yang, Xueli Zhao, Lei Chen, Fujun Gou, Songlin Liu

Summary: The blanket, as a key component of the fusion reactor, plays important roles in breeding tritium, shielding neutrons, and extracting thermal energy for electricity generation. Understanding the characteristics of gas-liquid two-phase flow and mass transfer is essential for optimizing the design of tritium extraction units in the blanket.

ANNALS OF NUCLEAR ENERGY (2024)

Article Nuclear Science & Technology

Gas phase interactions between tellurium and organic material in severe nuclear accident scenarios

Anna-Elina Pasi, Teemu Karkela, Fredrik Borjesson Sanden, Unto Tapper, Tuula Kajolinna, Christian Ekberg

Summary: This study investigates the gas-phase interactions between tellurium and organic material under severe nuclear accident conditions. The results show that there is interaction between tellurium aerosols and organic material, leading to an increase in the gaseous fraction and changes in XPS spectra. Although the exact species are not identified, these findings raise questions about the behavior of tellurium and its reactions with organic material in severe accident conditions.

ANNALS OF NUCLEAR ENERGY (2024)

Article Nuclear Science & Technology

Numerical analysis of fluid force on orifice structure of valve disc for nuclear globe valve

Ao Zhang, Qingye Li, Chaoyong Zong, Fuwen Liu, Tianhang Xue, Jian Xiao, Xueguan Song

Summary: In this study, a high-fidelity computational fluid dynamics model was established to investigate the flow characteristics of a novel balanced globe valve. The study found that the size of the throttle orifice and valve disc displacement have a significant impact on fluid force. The findings provide a basis for the design and dynamic control of globe valves, and also have potential value for energy utilization.

ANNALS OF NUCLEAR ENERGY (2024)

Article Nuclear Science & Technology

Accuracy analysis of RANS turbulent models on predicting thermal stratification in the SUPERCAVNA facility

Wenbo Li, Yunqing Bai, Shuai Zhang, Yang Li, Ming Jin, Chunjing Li

Summary: In this study, a 3D-CFD model based on the SUPERCAVNA facility was established to analyze thermal stratification in liquid-metal-cooled nuclear reactors. The results show that the SKE model is the most accurate in predicting temperature distribution, and further parametric studies were conducted.

ANNALS OF NUCLEAR ENERGY (2024)

Article Nuclear Science & Technology

Fragility evaluation of nuclear containment structure subjected to earthquake and subsequent internal pressure

Song Jin, Di Jiang, Dongmei Wang, Shaojie Wang, Zhen Wang

Summary: This study presents the fragility evaluation of a nuclear containment structure subjected to earthquake and subsequent internal pressure sequence. Nonlinear finite element model and ground motion records are used to analyze the nonlinear response and fragility of the structure. Results show that the distribution of maximum strain and displacement of the structure under earthquake and subsequent pressure are significantly different, with displacement distribution related to ground motion intensity levels.

ANNALS OF NUCLEAR ENERGY (2024)

Article Nuclear Science & Technology

Integration of Level 3 probabilistic risk assessment for nuclear power plants with transportation simulation considering earthquake hazards

Kazumasa Shimada, Tatsuya Sakurahara, Pegah Farshadmanesh, Seyed Reihani, Zahra Mohaghegh

Summary: This research improves the realism of Level 3 probabilistic risk assessment for nuclear power plants by modeling the evacuation behavior of residents and incorporating two advancements. The first advancement uses evacuation speed from a transportation simulation code as input to the Level 3 PRA code, enabling explicit incorporation of spatiotemporal evacuation processes. The second advancement incorporates the probability of seismic damage to roadway bridges into Level 3 PRA and calculates evacuation routes and speeds considering the impact of seismic damage.

ANNALS OF NUCLEAR ENERGY (2024)

Article Nuclear Science & Technology

Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project

F. Mascari, A. Bersano, M. Massone, G. Agnello, O. Coindreau, S. Beck, L. Tiborcz, S. Paci, M. Angelucci, L. E. Herranz, R. Bocanegra, Y. Pontillon, M. Berdai, O. Cherednichenko, A. Iskra, M. Nudi, P. Groudev, P. Petrova, F. Kretzschmar, F. Gabrielli, Z. Kanglong, V. Vileiniskis, T. Kaliatka, J. Kalilainen, M. Malicki, D. Gumenyuk, Y. Vorobyov, O. Kotsuba, P. Dejardin, M. Di Giuli, R. Thomas, I. V. Ivanov, F. Giannetti, M. D'Onorio, G. Caruso, M. Salay, T. Sevon

Summary: The MUSA project aims to analyze uncertainties and sensitivities associated with severe accidents using a harmonized approach, particularly focusing on source term figures of merit. The project applied and tested uncertainty quantification methodologies using the PHEBUS FPT1 test. The study found that scripting for coupling SA codes and uncertainty tools can increase flexibility, and careful consideration should be given to selecting the input uncertain parameters.

ANNALS OF NUCLEAR ENERGY (2024)

Article Nuclear Science & Technology

Effects of transient fission gas release on rod balloon burst behavior during a loss-of-coolant accident

Ian Greenquist, Nathan Capps

Summary: The US nuclear energy industry is investigating strategies to increase reactor operating cycle to 24 months. Multiphysics simulations tools and methodologies are being developed to predict the effects of this change during transient events such as loss-of-coolant accidents (LOCAs).

ANNALS OF NUCLEAR ENERGY (2024)

Article Nuclear Science & Technology

TARS: A parallel tetrahedral discontinuous finite element code for the solution of the discrete ordinates neutron transport equation

Guangchun Zhang, Hu Zhang

Summary: In this study, a neutron transport code called TARS is introduced, which is based on the discrete-ordinates discontinuous finite element method. TARS provides accurate and efficient solutions to the neutron transport equation, addressing existing challenges in the field. The evaluation results demonstrate that TARS generates highly accurate solutions and achieves high parallel computation efficiency.

ANNALS OF NUCLEAR ENERGY (2024)

Article Nuclear Science & Technology

Development and verification of a one-dimensional collision probability based neutron transport code to model axially heterogeneous cylindrical vessels containing aqueous and organic plutonium nitrate

J. R. Daniels, M. M. R. Williams, M. D. Eaton

Summary: This paper presents the development and verification of a collision probability (CP) code for neutron transport in slabs and cylinders. The CP code is particularly useful for modelling layered systems of aqueous and organic plutonium nitrate. The code provides a computationally inexpensive alternative to higher fidelity codes like MCNP. It is effective for slab geometries with at least 0.7 g cm-2 plutonium, but its approximation for heterogeneous cylinders can lead to overestimation of neutron leakage. Increasing the cylinder radius to 40.0 cm improves the accuracy for systems with at least 2.75 kg plutonium. However, the code's accuracy decreases when modelling cylindrical geometries with dished ends and low plutonium content.

ANNALS OF NUCLEAR ENERGY (2024)

Article Nuclear Science & Technology

Angular distribution uncertainty influence in a large sodium-cooled fast reactor with mixed-oxide fuel

Alexander A. Ryzhkov, Georgy V. Tikhomirov, Mikhail Yu. Ternovykh

Summary: This paper analyzes the impact of nuclear data uncertainties on the safety of advanced reactors, with a specific focus on angular distribution uncertainties. Through sensitivity and uncertainty analysis, key parameters for MOX3600 are identified, and a comparison of different libraries' uncertainties on the eigenvalue is performed.

ANNALS OF NUCLEAR ENERGY (2024)

Article Nuclear Science & Technology

FEMFFUSION and its verification using the C5G7 benchmark

Y. Fontenla, A. Vidal-Ferrandiz, A. Carreno, D. Ginestar, G. Verdu

Summary: FEMFFUSION is an open source code that solves the multigroup neutron transport equation using the diffusion and the SPN approximations. It uses the finite element method to handle various geometries and problem dimensions, and has been verified against the C5G7 benchmark.

ANNALS OF NUCLEAR ENERGY (2024)

Article Nuclear Science & Technology

Testing of fiber optic based sensors for advanced reactors in the Texas A&M University TRIGA reactor

J. Tyler Gates, Pavel V. Tsvetkov

Summary: The Optical Fiber Based Gamma Thermometer utilizes optical fiber as a distributed temperature sensor to measure the temperature of a thermal mass undergoing gamma heating and calculate the gamma flux data. This technology shows promise in determining the local power density within a nuclear reactor core and provides an unparalleled level of precision in reactor power measurement.

ANNALS OF NUCLEAR ENERGY (2024)

Article Nuclear Science & Technology

Extending TRANSURANUS burnup model for AGR-like FHR fuel design

A. de Lara, A. Schubert, E. Shwageraus, P. Van Uffelen

Summary: This study presents a new methodology to derive the radial form factor in the TRANSURANUS burnup model using simulations. The proposed methodology can be applied to different types of reactors, including LWRs and HWRs, and is suitable for advanced technology fuels.

ANNALS OF NUCLEAR ENERGY (2024)

Article Nuclear Science & Technology

Iodine source term assessment under DBA SGTR accident scenario

A. Bousbia Salah, M. Di Giuli, P. Foucaud, R. Iglesias, A. Malkhasyan, M. Salmaoui, L. E. Herranz

Summary: In the framework of the R2CA project, the application of advanced codes for evaluating radiological release under design basis accidents was considered. The study focused on a specific scenario and assessed the results obtained by different organizations using different computational tools and approaches. The outcomes highlighted modeling differences and challenges in carrying out such analysis.

ANNALS OF NUCLEAR ENERGY (2024)