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Advanced Multi-Physics Modeling, Simulation, and Optimization for Nuclear Technology
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Advanced Multi-Physics Modeling, Simulation, and Optimization for Nuclear Technology

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

Deadline for manuscript submissions: 16 May 2024 | Viewed by 6639

Special Issue Editors

Dr. Pablo Romojaro

E-Mail Website
Guest Editor
Belgian Nuclear Research Centre (SCK CEN), 200, 2400 Mol, Belgium
Interests: reactor physics; computer modeling; nuclear science; Monte Carlo simulation; radiation protection; radioactivity; reactors; radiation physics
Dr. Gašper Žerovnik

E-Mail Website
Guest Editor
Jožef Stefan Institute, Jamova cesta 39, SI-1000 Ljubljana, Slovenia
Interests: reactor physics; computer modeling; nuclear science; Monte Carlo simulation; radiation protection; radioactivity; reactors; experimental nuclear physics; radiation physics
Dr. Aljaž Čufar

E-Mail Website
Guest Editor
Jožef Stefan Institute, Jamova cesta 39, SI-1000 Ljubljana, Slovenia
Interests: reactor physics; computer modeling; radiation detection nuclear science; Monte Carlo simulation; radiation protection; radioactivity; reactors; radiation physics

Special Issue Information

Dear Colleagues,

Due to the challenges related to the effects of global warming, research and development in the field of reliable low-carbon energy sources is more important than ever. In addition, independence from fossil-based energy sources has other benefits, including reduced sensitivity of the reliability of the energy supply to geopolitical conflicts. Whereas energy production from nuclear fission is in principle well-known, proven, and has reliably been used for decades, the drive to continuously improve upon these foundations remains. Recent advances in computational power enable simultaneous development and implementation of more sophisticated numerical methods. These can result in more accurate and reliable simulations of complex systems, contributing to an improved efficiency and safety of nuclear installations. On the other hand, nuclear fusion technology has been undergoing immense advances. The advancements in existing facilities as well as the research potential of new and planned facilities provide hope for its commercial implementation in the following decades. Commercial fusion could thus become another important tool for tackling the energy and climate crises in the second half of the century.

This Special Issue aims to include the most recent advances in methodologies for modeling and analysis of nuclear fission and fusion systems. The topics of interest include but are not limited to the following:

Fields:

  • Neutron physics for fission and fusion;
  • Multi-physics: material science, nuclear fuel performance, thermal hydraulics, activation;
  • Nuclear data;

Methods:

  • Advanced: AI, machine learning, variance reduction, automatized modeling;
  • Sensitivity analysis, uncertainty quantification;

Technologies:

  • Current and new reactor technologies;
  • Accelerator driven systems (ADS);
  • Fusion-related facilities: ITER, DEMO, IFMIF-DONES, etc.

Dr. Pablo Romojaro
Dr. Gašper Žerovnik
Dr. Aljaž Čufar
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

  • machine learning
  • artificial intelligence
  • multi-physics
  • uncertainty/sensitivity analysis
  • nuclear fission
  • nuclear fusion
  • nuclear data

Published Papers (7 papers)

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Research

13 pages, 4130 KiB  
Article
An Investigation of Structural Strength of Nuclear Fuel Spacer Grid
by Naqeeb Hakam Adli and Ihn Namgung
Energies 2024, 17(2), 458; https://doi.org/10.3390/en17020458 - 17 Jan 2024
Viewed by 523
Abstract
This paper compares and discusses the methods for evaluation of the structural integrity of the mid spacer grid of nuclear fuel assembly via a finite element analysis of 3D shell elements. The structural stiffness of the spacer grid is determined by applying either [...] Read more.
This paper compares and discusses the methods for evaluation of the structural integrity of the mid spacer grid of nuclear fuel assembly via a finite element analysis of 3D shell elements. The structural stiffness of the spacer grid is determined by applying either force or deformation as loads onto the spacer grid for both the square load and shear load directions. This study is an extension of a single-cell strength analysis of a spacer. External events such as seismic activities that might happen in a nuclear reactor are able to transfer loads onto nuclear components in random directions, which can be broken down into square and shear loadings. The structural strength indicated by the force reaction against the input displacement load was proven to be smaller such that the same displacement square load is around 260 times greater than the shear load. Due to the weakness in shear stiffness, the maintenance of a spacer grid structure is more vulnerable against out-of-plane loads. This indicates that the shear load needs to be considered in studies of fuel assembly integrity assessment for newly developing fuel design, as well as existing fuel assembly designs. Full article
(This article belongs to the Special Issue Advanced Multi-Physics Modeling, Simulation, and Optimization for Nuclear Technology)
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20 pages, 2711 KiB  
Article
Fuel Performance Analysis of Fast Flux Test Facility MFF-3 and -5 Fuel Pins Using BISON with Post Irradiation Examination Data
by Kyle M. Paaren, Micah Gale, David Wootan, Pavel Medvedev and Douglas Porter
Energies 2023, 16(22), 7600; https://doi.org/10.3390/en16227600 - 16 Nov 2023
Cited by 2 | Viewed by 600
Abstract
Using the BISON fuel-performance code, simulations were conducted of an automated process to read initial and operating conditions from the Pacific Northwest National Laboratory (PNNL) database and reports, which contain metallic-fuel data from the Fast Flux Test Facility (FFTF) MFF Experiments. This work [...] Read more.
Using the BISON fuel-performance code, simulations were conducted of an automated process to read initial and operating conditions from the Pacific Northwest National Laboratory (PNNL) database and reports, which contain metallic-fuel data from the Fast Flux Test Facility (FFTF) MFF Experiments. This work builds on previous modeling efforts involving 1977 EBR-II metallic fuel pins from experiments. Coupling the FFTF PNNL reports to BISON allowed for all 338 pins from MFF-3 and MFF-5 campaigns to be simulated. Each BISON simulation contains unique power and flux histories, axial power and flux profiles, and coolant-channel flow rates. Fission-gas release (FGR), fuel axial swelling, cladding profilometry, and burnup were all simulated in BISON and compared to available post-irradiation examination (PIE) data. Cladding profilometry, FGR, and fuel axial swelling simulation results for full-length MFF metallic pins were found to be in agreement with PIE measurements using FFTF physics and models used previously for EBR-II simulations. The main two peaks observed within the cladding profilometry were able to be simulated, with fuel-cladding mechanical interaction (FCMI), fuel-cladding chemical interaction (FCCI), and thermal and irradiation-induced creep being the cause. A U-Pu-Zr hot-pressing model was included in this work to allow pore collapse within the fuel matrix. This allowed better agreement between BISON-simulated cladding profilometry and PIE measurements for the peak caused by FCMI. This work shows that metallic fuel models used to accurately represent fuel performance for smaller EBR-II pins may be used for full-length metallic fuel, such as FFTF MFF assemblies and the Versatile Test Reactor (VTR). As new material models and PIE measurements become available, FFTF MFF assessment cases will be reassessed to further BISON model development. Full article
(This article belongs to the Special Issue Advanced Multi-Physics Modeling, Simulation, and Optimization for Nuclear Technology)
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19 pages, 15581 KiB  
Article
Comparison of Zirconium Redistribution in BISON EBR-II Models Using FIPD and IMIS Databases with Experimental Post Irradiation Examination
by Kyle M. Paaren, Spencer Christian, Luca Capriotti, Assel Aitkaliyeva and Douglas Porter
Energies 2023, 16(19), 6817; https://doi.org/10.3390/en16196817 - 26 Sep 2023
Cited by 1 | Viewed by 747
Abstract
Metallic fuels have seen increased interest for future sodium fast reactors due to their material properties: high thermal conductivities and advantageous neutronic properties allow for greater fission densities. One drawback to typical metallic fuels is zirconium redistribution, which impacts this advantageous material and [...] Read more.
Metallic fuels have seen increased interest for future sodium fast reactors due to their material properties: high thermal conductivities and advantageous neutronic properties allow for greater fission densities. One drawback to typical metallic fuels is zirconium redistribution, which impacts this advantageous material and its neutronic properties. Unfortunately, the processes behind zirconium migration behavior are understood using first principles, so before these fuels are implemented in future fast reactors, characterization and fuel qualification regimes must be completed. These activities can be supported through the use of robust modeling using the most accurate empirical models currently available to fuel researchers around the world. The tool that allows researchers to model this complex coupled thermo-mechanical behavior and nuclear properties is BISON. Additionally, BISON model parameters need to be compared against PIE measurements. The current work utilizes two fuel pins from EBR-II experiment X441 to optimize various model parameters, including porosity correction factor, thermal conductivity, phase transition temperature, and diffusion coefficient multipliers, before implementing the final model for seven fuel pins with differing characteristics. To properly evaluate the BISON simulations, the results are compared to PIE metallography data for each fuel pin, to ensure the zirconium redistribution is properly reflected in the simulation results. Six out of seven analyzed fuel pins demonstrate good agreement between the metallography images and BISON results, showing alignment of the Zr-rich, Zr-depleted, and moderately Zr-enriched zones at various axial heights along the fuel pins. Further work is needed to refine the model parameters for general pin use. Full article
(This article belongs to the Special Issue Advanced Multi-Physics Modeling, Simulation, and Optimization for Nuclear Technology)
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13 pages, 1856 KiB  
Article
Investigation of the Segregation of Radiocesium from Contaminated Aqueous Waste Using AMP-PAN Extraction Chromatography
by Taisir Khudhair Abbas, Thaeerh Tariq Abdulghafoor, Ali Hassan Aziz, Saad Al-Saadi, Takrid Munam Nafae, Khalid Turki Rashid and Qusay F. Alsalhy
Energies 2023, 16(18), 6544; https://doi.org/10.3390/en16186544 - 12 Sep 2023
Cited by 2 | Viewed by 1084
Abstract
Removing the hazardous and unstable radioactive isotopes has been considered an arduous task, though they are in minimal concentrations. Cesium-137 (137Cs+) is a primary fission product produced by nuclear processes. Even at low concentrations, such radioactive material is a [...] Read more.
Removing the hazardous and unstable radioactive isotopes has been considered an arduous task, though they are in minimal concentrations. Cesium-137 (137Cs+) is a primary fission product produced by nuclear processes. Even at low concentrations, such radioactive material is a menacing source of contaminants for the environment. The current study aims to separate 137Cs+ from a real contaminated aqueous solution via an ion exchange mechanism using ammonium molybdophosphate–polyacrylonitrile (AMP-PAN) resin loaded in an extraction chromatographic column that possesses considerable selectivity toward cesium ion (Cs+) due to the specific ion exchange between 137Cs+ and NH4+. Additionally, the proposed interaction mechanism between 137Cs+ with APM-PAN resin has been illustrated in this study. The results disclosed that the optimum efficient removal of 137Cs+ (91.188%) was obtained by the AMP-PAN resin using 2 g·L−1, while the distribution adsorption coefficient (129.359 mL·g−1) was at pH 6. The isothermal adsorption process was testified through the Langmuir and Freundlich models. The estimated maximum adsorption capacity reached 140.81 ± 21.3 mg·g−1 for the Freundlich isotherm adsorption model. Finally, AMP-PAN resin could eliminate 137Cs+ from water effectively through adsorption. Full article
(This article belongs to the Special Issue Advanced Multi-Physics Modeling, Simulation, and Optimization for Nuclear Technology)
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21 pages, 5221 KiB  
Article
Dynamic Dose-Based Emergency Evacuation Model for Enhancing Nuclear Power Plant Emergency Response Strategies
by Huifang Miao, Guoming Zhang, Peizhao Yu, Chunsen Shi and Jianxiang Zheng
Energies 2023, 16(17), 6338; https://doi.org/10.3390/en16176338 - 31 Aug 2023
Cited by 1 | Viewed by 820
Abstract
The safe evacuation of residents near a nuclear power plant during a nuclear accident is vital for emergency response planning. To tackle this challenge, considering the dynamic dispersion of radioactive materials in the atmosphere and its impact on evacuation routes under different meteorological [...] Read more.
The safe evacuation of residents near a nuclear power plant during a nuclear accident is vital for emergency response planning. To tackle this challenge, considering the dynamic dispersion of radioactive materials in the atmosphere and its impact on evacuation routes under different meteorological conditions is crucial. This paper develops a dynamic dose-based emergency evacuation model (DDEEM), which is an efficient and optimized nuclear accident evacuation model based on dynamic radiological dose calculation, utilizing an improved A* algorithm to determine optimal evacuation routes. The DDEEM takes into account the influence of radiological plume dispersion and path selection on evacuation effectiveness. This study employs the DDEEM to assess radiological consequences and evacuation strategies for students residing 5 km from a Chinese nuclear power plant. Under various meteorological conditions, including the three typical meteorological conditions, random ordered and random unordered meteorological sequences, optimal routes obtained through the DDEEM effectively reduce radiological dose exposure and mitigate radiation hazards. The results indicate that all evacuation paths generated by the DDEEM have a maximum dose of less than 1 mSv. Through simulations, the model’s effectiveness and reliability in dynamic radiological environments in terms of radiological consequences and evacuation analysis is verified. The research provides valuable insights and a practical tool for nuclear power plant emergency decision-making, enhancing emergency management capabilities during nuclear accidents. The DDEEM offers crucial technical support and a solid foundation for developing effective emergency response strategies. Full article
(This article belongs to the Special Issue Advanced Multi-Physics Modeling, Simulation, and Optimization for Nuclear Technology)
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15 pages, 7837 KiB  
Article
Water Chemistry Impact on Activated Corrosion Products: An Assessment on Tokamak Reactors
by Martina Molinari, Matteo D’Onorio, Giovanni Mariano, Nicholas Terranova and Gianfranco Caruso
Energies 2023, 16(12), 4726; https://doi.org/10.3390/en16124726 - 15 Jun 2023
Viewed by 779
Abstract
Activated Corrosion Product (ACP) formation and deposition pose a critical safety issue for nuclear fusion reactors. The working fluid transports the ACPs towards regions accessible by worker personnel, i.e., the steam generator. The code OSCAR-Fusion has been developed by the CEA (France) to [...] Read more.
Activated Corrosion Product (ACP) formation and deposition pose a critical safety issue for nuclear fusion reactors. The working fluid transports the ACPs towards regions accessible by worker personnel, i.e., the steam generator. The code OSCAR-Fusion has been developed by the CEA (France) to evaluate the ACP generation and transport in closed water-cooled loops for fusion application. This work preliminary assesses the impact of water chemistry on the transport, precipitation, and deposition of corrosion products for the EU-DEMO divertor Plasma Facing Unit Primary Heat Transfer System. Sensitivity analyses and uncertainty quantification are needed due to the multi-physics phenomena involved in ACP formation and transport. The OSCAR-Fusion/RAVEN code coupling developed by the Sapienza University of Rome and ENEA are used. This work presents the perturbation results of different parameters chosen for a closed water-cooled loop considering a continuous scenario of 1888 days. The aim of this work is to preliminarily assess the variation of build-up of ACPs, perturbing the alkalizing agent concentration into the coolant, and the corrosion and release rates of different materials. The assessment of ACP formation deposition and transport is fundamental for source term identification, reduction of radiation exposure assessment, maintenance plan definition, design optimization, and waste management. Full article
(This article belongs to the Special Issue Advanced Multi-Physics Modeling, Simulation, and Optimization for Nuclear Technology)
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25 pages, 11615 KiB  
Article
Development of a Thermal-Hydraulic Model for the EU-DEMO Tokamak Building and LOCA Simulation
by Matteo D’Onorio, Tommaso Glingler, Maria Teresa Porfiri, Danilo Nicola Dongiovanni, Sergio Ciattaglia, Curt Gliss, Joëlle Elbez-Uzan, Pierre Cortes and Gianfranco Caruso
Energies 2023, 16(3), 1149; https://doi.org/10.3390/en16031149 - 20 Jan 2023
Cited by 2 | Viewed by 1302
Abstract
The EU-DEMO must demonstrate the possibility of generating electricity through nuclear fusion reactions. Moreover, it must denote the necessary technologies to control a powerful plasma with adequate availability and to meet the safety requirements for plant licensing. However, the extensive radioactive materials inventory, [...] Read more.
The EU-DEMO must demonstrate the possibility of generating electricity through nuclear fusion reactions. Moreover, it must denote the necessary technologies to control a powerful plasma with adequate availability and to meet the safety requirements for plant licensing. However, the extensive radioactive materials inventory, the complexity of the plant, and the presence of massive energy sources require a rigorous safety approach to fully realize fusion power’s environmental advantages. The Tokamak building barrier design must address two main issues: radioactive mass transport hazards and energy-related or pressure/vacuum hazards. Safety studies are performed in the frame of the EUROfusion Safety And Environment (SAE) work package to support design improvement and evaluate the thermal-hydraulic behavior of confinement building environments during accident conditions in addition to source term mobilization. This paper focuses on developing a thermal-hydraulic model of the EU-DEMO Tokamak building. A preliminary model of the heat ventilation and air conditioning system and vent detritiation system is developed. A loss-of-coolant accident is studied by investigating the Tokamak building pressurization, source term mobilization, and release. Different nodalizations were compared, highlighting their effects on source term estimation. Results suggest that the building design should be improved to maintain the pressure below safety limits; some mitigative systems are preliminarily investigated for this purpose. Full article
(This article belongs to the Special Issue Advanced Multi-Physics Modeling, Simulation, and Optimization for Nuclear Technology)
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