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Advances in Nuclear Energy: Recent Progress on Thermal Hydraulics in Nuclear Reactors Multiphysics Applications and Coupling Schemes

A special issue of Energies (ISSN 1996-1073). This special issue belongs to the section "B4: Nuclear Energy".

Deadline for manuscript submissions: closed (31 March 2023) | Viewed by 5269

Special Issue Editors

Dr. Han Zhang

E-Mail Website
Guest Editor
Key Laboratory of Advanced Reactor Engineering and Safety, Ministry of Education, Institute of Nuclear and New Energy Technology (INET), Tsinghua University, Beijing, China
Interests: high-temperature gas cooled reactor; thermal hydraulics; computational fluid dynamics and multiphysics coupling algorithms
Prof. Dr. Annalisa Manera

E-Mail Website
Guest Editor
Department of Mechanical and Process Engineering, ETH-Zurich, Zurich, Switzerland
Interests: experimental two-phase flow; thermal hydraulics; computational fluid dynamics and nuclear reactor safety analysis
Prof. Dr. Raad Issa

E-Mail Website
Guest Editor
Department of Mechanical Engineering, Imperial College London, London, UK
Interests: computational fluid dynamics and two-phase flows

Special Issue Information

Dear Colleagues,

The accurate prediction of nuclear thermal hydraulics behaviour is a fundamental, but important issue for nuclear reactor design and safety analysis. Comprehensive high-fidelity thermal hydraulics modelling is a powerful numerical tool for detailed analysis of current and advanced reactor designs. Moreover, thermal hydraulics usually couples with other physical fields, such as neutronics, mechanics, chemistry, etc., leading to a comprehensive large-scale nonlinear system. This is still a challenging task in the nuclear engineering community. With the development of computational capability, there has been exponentially growing interest in topics related to advanced numerical methods and tools in thermal hydraulics modelling and its coupling problems to pursue a realistic description of the physical behaviour without conservative assumptions. Recently, emerging numerical methods and practical simulation tools have significantly promoted the development of related fields.

The Guest Editors are inviting submissions to a Special Issue of Energies on “Advances in Nuclear Energy: Recent Progress in Thermal Hydraulics in Nuclear Reactors Multiphysics Applications and Coupling Schemes”. This Special Issue invites all researchers from academia and industry on nuclear reactors to share their latest and significant achievements and promote development in the area of thermal hydraulics and multiphysics coupling modelling. Original research work as well as critical review articles on the topics mentioned above are welcomed, and other related studies are also solicited.

Dr. Han Zhang
Prof. Dr. Annalisa Manera
Prof. Dr. Raad Issa
Guest Editors

Manuscript Submission Information

Manuscripts should be submitted online at www.mdpi.com by registering and logging in to this website. Once you are registered, click here to go to the submission form. Manuscripts can be submitted until the deadline. All submissions that pass pre-check are peer-reviewed. Accepted papers will be published continuously in the journal (as soon as accepted) and will be listed together on the special issue website. Research articles, review articles as well as short communications are invited. For planned papers, a title and short abstract (about 100 words) can be sent to the Editorial Office for announcement on this website.

Submitted manuscripts should not have been published previously, nor be under consideration for publication elsewhere (except conference proceedings papers). All manuscripts are thoroughly refereed through a single-blind peer-review process. A guide for authors and other relevant information for submission of manuscripts is available on the Instructions for Authors page. Energies is an international peer-reviewed open access semimonthly journal published by MDPI.

Please visit the Instructions for Authors page before submitting a manuscript. The Article Processing Charge (APC) for publication in this open access journal is 2600 CHF (Swiss Francs). Submitted papers should be well formatted and use good English. Authors may use MDPI's English editing service prior to publication or during author revisions.

Keywords

  •  thermal hydraulics
  •  subchannel method
  •  computational fluid dynamics
  •  two-phase flow
  •  nuclear safety analysis
  •  severe accident analysis
  •  hydrogen distribution
  •  multiphysics coupling problem
  •  multiscale coupling problem
  •  nonlinear and linear solver
  •  data-driven model
  •  reduced order model
  •  uncertainty analysis, sensitively analysis

Published Papers (4 papers)

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Research

14 pages, 1945 KiB  
Article
A Modified JFNK for Solving the HTR Steady State Secondary Circuit Problem
by Zhuo Jiang, Yingjie Wu, Han Zhang, Lixun Liu, Jiong Guo and Fu Li
Energies 2023, 16(5), 2252; https://doi.org/10.3390/en16052252 - 26 Feb 2023
Viewed by 1089
Abstract
A nuclear power plant is a complex coupling system, which features multi-physics coupling between reactor physics and thermal-hydraulics in the reactor core, as well as the multi-circuit coupling between the primary circuit and the secondary circuit by the shared steam generator (SG). Especially [...] Read more.
A nuclear power plant is a complex coupling system, which features multi-physics coupling between reactor physics and thermal-hydraulics in the reactor core, as well as the multi-circuit coupling between the primary circuit and the secondary circuit by the shared steam generator (SG). Especially in the pebble-bed modular HTR nuclear power plant, different nuclear steam supply modules are further coupled together through the shared main steam pipes and the related equipment in the secondary circuit, since the special configuration of multiple reactor modules connects to a steam turbine. The JFNK (Jacobian-Free Newton–Krylov) method provides a promising coupling framework to solve the whole HTR nuclear power plant problem, due to its excellent convergence rate and strong robustness. In this work, the JFNK method was modified and applied to the steady-state calculation of the HTR secondary circuit, which plays an important role in simultaneous solutions for the whole HTR nuclear power plant. The main components in the secondary circuit included SG, steam turbine, condenser, feed pump, high/low-pressure heat exchanger, deaerator, as well as the extraction steam from the steam turbine. The results showed that the JFNK method can effectively solve the steady state issue of the HTR secondary circuit. Moreover, the JFNK method could converge well within a wide range of initial values, indicating its strong robustness. Full article
(This article belongs to the Special Issue Advances in Nuclear Energy: Recent Progress on Thermal Hydraulics in Nuclear Reactors Multiphysics Applications and Coupling Schemes)
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17 pages, 2329 KiB  
Article
Decay Branch Ratio Sampling Method with Dirichlet Distribution
by Yizhen Wang, Menglei Cui, Jiong Guo, Han Zhang, Yingjie Wu and Fu Li
Energies 2023, 16(4), 1962; https://doi.org/10.3390/en16041962 - 16 Feb 2023
Viewed by 1108
Abstract
The decay branch ratio is evaluated nuclear data related to the decay heat calculation in reactor safety analysis. Decay branch ratio data are inherently subjected to the “sum-to-one” constraint, making it difficult to generate perturbed samples while preserving their suggested statistics in a [...] Read more.
The decay branch ratio is evaluated nuclear data related to the decay heat calculation in reactor safety analysis. Decay branch ratio data are inherently subjected to the “sum-to-one” constraint, making it difficult to generate perturbed samples while preserving their suggested statistics in a library of evaluated nuclear data. Therefore, a stochastic-sampling-based uncertainty analysis method is hindered in quantifying the uncertainty contribution of the decay branch ratio to the decay heat calculation. In the present work, two alternative sampling methods are introduced, based on Dirichlet and generalized Dirichlet distribution, to tackle the decay branch ratio sampling issue. The performance of the introduced methods is justified by three-branch decay data retrieved from ENDF/B-VIII.0. The results show that the introduced sampling methods are capable of generating branch ratio samples and preserving their suggested statistics in an evaluated nuclear data library while satisfying their inherent “sum-to-one” constraint. These decay-branch-ratio sampling methods are expected to be alternative procedures in conducting stochastic-sampling-based uncertainty analyses of the decay branch ratio in reactor simulations. Full article
(This article belongs to the Special Issue Advances in Nuclear Energy: Recent Progress on Thermal Hydraulics in Nuclear Reactors Multiphysics Applications and Coupling Schemes)
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19 pages, 2920 KiB  
Article
Simultaneous Solution of Helical Coiled Once-Through Steam Generator with High-Speed Water Property Library
by Yingjie Wu, Zhuo Jiang, Han Zhang, Lixun Liu, Huanran Tang, Jiong Guo and Fu Li
Energies 2023, 16(4), 1627; https://doi.org/10.3390/en16041627 - 6 Feb 2023
Viewed by 1212
Abstract
Efficient simulation of the helical coiled once-through steam generator (H-OTSG) is crucial in the design and safety analysis of the high-temperature gas-cooled reactor (HTGR). The physical property and phase transformation of water in the steam generator brings great challenges during simulation. The water [...] Read more.
Efficient simulation of the helical coiled once-through steam generator (H-OTSG) is crucial in the design and safety analysis of the high-temperature gas-cooled reactor (HTGR). The physical property and phase transformation of water in the steam generator brings great challenges during simulation. The water properties calculation routine occupies a large part of the computational time in the steam generator solution process. Thus, a thermohydraulic property library is developed based on the IAPWS-IF97 formulation in this work to reduce the computational cost. Here the formulation adopts the backward equation method to avoid iterations in thermodynamic property calculation. Moreover, two Newton-method-based simultaneous solutions are implemented as implicitly nonlinear solvers, including Jacobian-Free Newton–Krylov (JFNK) and Newton–Krylov (NK) methods, due to its excellent computational performance. These simultaneous solution algorithms are combined with the developed water property library to simulate the H-OTSG efficiently. The numerical analysis is performed based on the transient and steady-state cases of the HTR-10 steam generator. Successful simulations of HTR-10 steam generator cases demonstrate the capability of the newly developed method. Full article
(This article belongs to the Special Issue Advances in Nuclear Energy: Recent Progress on Thermal Hydraulics in Nuclear Reactors Multiphysics Applications and Coupling Schemes)
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17 pages, 17948 KiB  
Article
Numerical Calculation Scheme of Neutronics-Thermal-Mechanical Coupling in Solid State Reactor Core Based on Galerkin Finite Element Method
by Baoxin Yuan, Jie Zheng, Jian Wang, Herong Zeng, Wankui Yang, Huan Huang and Songbao Zhang
Energies 2023, 16(2), 659; https://doi.org/10.3390/en16020659 - 5 Jan 2023
Cited by 3 | Viewed by 1354
Abstract
It is of practical significance to study the multi-physical processes of solid state nuclear systems for device design, safety analysis, and operation guidance. This system generally includes three multi-physical processes: neutronics, heat transfer, and thermoelasticity. In order to analyze the multi-physical field behavior [...] Read more.
It is of practical significance to study the multi-physical processes of solid state nuclear systems for device design, safety analysis, and operation guidance. This system generally includes three multi-physical processes: neutronics, heat transfer, and thermoelasticity. In order to analyze the multi-physical field behavior of solid state nuclear system, it is necessary to analyze the laws of neutron flux, temperature, stress, and other physical fields in the system. Aiming at this scientific goal, this paper has carried out three aspects of work: (1) Based on Galerkin’s finite element theory, the governing equations of neutronics, heat transfer, and thermoelasticity have been established; (2) a neutronics-thermal-mechanical multi-physical finite element analysis code was developed and verified based on benchmark examples and third-party software for multi-physical processes; (3) for a solid state nuclear system with a typical heat pipe cooled reactor configuration, based on the analysis code developed in this work, the neutronics-thermal-mechanical coupling analysis was carried out, and the physical field laws such as neutron flux, temperature, stress, etc., of the device under the steady-state operating conditions were obtained; and (4) finally, the calculation results are discussed and analyzed, and the focus and direction of the next work are clarified. Full article
(This article belongs to the Special Issue Advances in Nuclear Energy: Recent Progress on Thermal Hydraulics in Nuclear Reactors Multiphysics Applications and Coupling Schemes)
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