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        <title>Frontiers in Nuclear Engineering | New and Recent Articles</title>
        <link>https://www.frontiersin.org/journals/nuclear-engineering</link>
        <description>RSS Feed for Frontiers in Nuclear Engineering | New and Recent Articles</description>
        <language>en-us</language>
        <generator>Frontiers Feed Generator,version:1</generator>
        <pubDate>2026-04-25T22:22:26.68+00:00</pubDate>
        <ttl>60</ttl>
        <item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1760157</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1760157</link>
        <title><![CDATA[Transformation of discrete fracture networks into equivalent continuum models for sparsely fractured rocks: comparing flow-based and geometry-based upscaling for flow and transport]]></title>
        <pubdate>2026-04-22T00:00:00Z</pubdate>
        <category>Original Research</category>
        <author>Caroline Darcel</author><author>Quentin Courtois</author><author>Urban Svensson</author><author>Romain Le Goc</author><author>Benoît Pinier</author><author>Jan-Olof Selroos</author><author>Philippe Davy</author>
        <description><![CDATA[In this study, we analyze the impact of transforming a discrete fracture network (DFN) model to an equivalent continuum model (ECM) on flow and solute transport characteristics. The analysis was conducted in a setting derived from – though simplified relative to – in-situ fracturing conditions at the Forsmark site. The geometrical structure of the DFN model considered is combined successively with a highly simplified transmissivity model (single constant value) in order to isolate spatial and structural effects, and with a more realistic model in which transmissivities depend on both fracture size and orientation (indirectly reflecting mechanical stress conditions). Two upscaling methods are considered: a simplified geometry-based method and a numerical flow-based method, in which local ECM cell properties are directly informed by local flow and transport simulations. For both approaches, we quantify the impact of ECM resolution. Specifically, we assess the sensitivity of local properties as well as local and global flow and transport indicators, to both the upscaling method and the ECM grid resolution. The results demonstrate that the transformation from DFN to ECM overestimates hydraulic conductivity, underestimates the geometric porosity but to a lesser extent and overestimates the transport porosity. This also artificially reduces flow path variability and tortuosity, except at very high resolutions. Consequently, average transfer times are shorter in ECMs than in DFNs, with discrepancies increasing as grid resolution coarsens. Similar trends are observed for first arrival times and mode (the peak of the distribution), but to a lesser extent. DFNs are also more likely to have very long transport times. Finally, we show that ECMs derived from geometry-based upscaling are highly sensitive to grid resolution, whereas flow-based upscaling exhibits significantly lower sensitivity.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1798989</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1798989</link>
        <title><![CDATA[Activity release calculation from the near-field of a repository for spent fuel]]></title>
        <pubdate>2026-04-22T00:00:00Z</pubdate>
        <category>Original Research</category>
        <author>Ping Chen</author><author>Qi Zhang</author><author>Chengming Shang</author>
        <description><![CDATA[It is essential for the safety assessment of a repository to analyze the release and transport of radionuclides from the near-field to the geosphere and subsequently to the surface environment. A new model has been developed in COMSOL Multiphysics based on input data from the safety case for the disposal of spent nuclear fuel at Olkiluoto. Complex processes, for example, nuclide decay, material corrosion, diffusion, sorption, and advection, are coupled in COMSOL Multiphysics. Under reasonable assumptions, the release rates of C-14, Cl-36, I-129, Cs-135, and Ni-59 are compared with results from simulations by GoldSim. Higher release rates are observed for these five isotopes. This discrepancy may arise from two factors. On the one hand, an excessively coarse grid in GoldSim enhances nuclide transport properties, leading to a greater accumulation of nuclides in the buffer in areas below the failed canister. On the other hand, important information is omitted in the 2D model. This suggests that the release rates calculated by GoldSim may require reconsideration. Although higher release rates were confirmed in this 3D model, the release rates of Tc-99, Np-237, Pu-239, and Pu-242 remain at low levels after 106 years (the timeframe for safety assessment in Finland and Sweden). Further development is possible in COMSOL Multiphysics, such as the replacement of spent fuel with vitrified glass and the implementation of a chemical reaction module. With this new model, greater confidence is achieved in the calculation of radionuclide release and transport. This is crucial for the safety assessment of repositories.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1771702</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1771702</link>
        <title><![CDATA[Research on a strongly generalizable fault diagnosis method based on adversarial transfer learning]]></title>
        <pubdate>2026-04-13T00:00:00Z</pubdate>
        <category>Original Research</category>
        <author>Biwei Zhu</author><author>Zhiguang Deng</author><author>Xuemei Wang</author><author>Sijie Xu</author><author>Chenlong Dong</author>
        <description><![CDATA[IntroductionShallow machine learning algorithms exhibit low efficiency in fault diagnosis under the conditions of small-sample and unlabeled data. To address this critical problem, this paper focuses on developing an effective fault diagnosis method suitable for cross-reactor-type scenarios, which is of great significance for improving the safety and operational level of nuclear power plants.MethodsA cross-reactor-type fault diagnosis method based on adversarial transfer learning is proposed. By integrating deep learning and transfer learning techniques, a hybrid domain-adversarial learning model is constructed. The overall loss function of the model is designed to effectively extract transferable features between related reactor types, and corresponding validation experiments are carried out to verify the model's feasibility and effectiveness.ResultsThe experimental validation shows that the proposed hybrid domain-adversarial learning model can effectively extract transferable features across different reactor types, which solves the problem of low efficiency of shallow machine learning algorithms in fault diagnosis under small-sample and unlabeled data conditions. The model achieves reliable fault diagnosis performance in cross-reactor-type scenarios.DiscussionWhen applied to cross-reactor-type nuclear power plant fault diagnosis, the research findings can significantly enhance the safety of nuclear power plants, improve their economic performance and operational efficiency. Furthermore, this research effectively promotes the intelligence level and autonomous decision-making capabilities of nuclear power plants, providing a valuable technical reference for the intelligent development of the nuclear power industry.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1836941</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1836941</link>
        <title><![CDATA[Editorial: Advanced modeling techniques in radioactive waste disposal]]></title>
        <pubdate>2026-04-07T00:00:00Z</pubdate>
        <category>Editorial</category>
        <author>Yuankai Yang</author><author>Tao Wu</author>
        <description></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1823864</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1823864</link>
        <title><![CDATA[Editorial: Analytical methods in nuclear forensics]]></title>
        <pubdate>2026-04-01T00:00:00Z</pubdate>
        <category>Editorial</category>
        <author>Kattathu J. Mathew</author><author>Amy E. Hixon</author><author>Matthew Higginson</author>
        <description></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1771859</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1771859</link>
        <title><![CDATA[Validation of SIMULATE5-K and CASMO5 with the SPERT-III E-Core]]></title>
        <pubdate>2026-03-20T00:00:00Z</pubdate>
        <category>Original Research</category>
        <author>William Dawn</author><author>Gerardo Grandi</author><author>Tamer Bahadir</author>
        <description><![CDATA[SIMULATE5-K (S5K) is the newest state-of-the-art, best-estimate, transient reactor analysis software developed by Studsvik Scandpower, Inc. (SSP). When used in conjunction with CASMO5 to generate multi-group neutronic data for steady-state and transient calculations, S5K can be used to accurately model reactor transient conditions in Pressurized Water Reactors (PWRs) and Boiling Water Reactors (BWRs). Recently, the methods in S5K and CASMO5 were validated by simulating reactor transients from the SPERT-III E-core experiments. These experiments were performed on a small Light Water Reactor (LWR) core and were designed to resemble Reactivity Insertion Accidents (RIAs) in PWRs. Overall, the results calculated with S5K agree well with the experimentally measured data and any differences are much smaller than the reported uncertainties in the measurements, especially the uncertainty in the initial condition. Additionally, S5K supports general multi-group time-dependent neutron diffusion calculations and the SPERT-III E-core experiments were used to show that there were no obvious trends or discrepancies when the two-, four-, and eight-group calculations were compared.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1757155</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1757155</link>
        <title><![CDATA[Shielding design for IECF devices: ensuring safety through material analysis]]></title>
        <pubdate>2026-03-16T00:00:00Z</pubdate>
        <category>Original Research</category>
        <author>Edward Martin</author><author>Thomas B. Scott</author><author>Mahmoud Bakr</author>
        <description><![CDATA[Inertial Electrostatic Confinement Fusion (IECF) devices have garnered increased recognition for their potential as compact, portable neutron sources for use in the generation of medical isotopes and various neutron-based interrogation techniques. This study investigates the shielding requirements for a laboratory enclosure that houses a deuterium-deuterium (DD) fueled IECF device. The simulation framework was first validated by reproducing the ambient dose equivalent, H*(10), conversion coefficient reference values, confirming the suitability of Geant4 for dose deposition measurements. Simulations were then used to evaluate neutron moderation and removal in various shielding materials, investigating five different concrete constituents and water, with the performance assessed relative to UK Ionising Radiations Regulations 2017 (IRR17) dose-rate limits. Neutron and gamma fluences were tallied in defined volumes of 40cm3, H*(10) measurements were then calculated using ICRP 74 conversion coefficients. The simulation results show that an IECF device can be operated safely at a neutron rate of 1×105ns−1 within public dose limits, recording <500nSvh−1 at a distance of 1.6m, with 10cm of all concretes tested other than Barite (Heavy) concrete, which measured 501nSvh−1. The results also show that a safe environment for radiation workers can be constructed, allowing the device to be operated at 1×107ns−1 if 30cm of water or ordinary concrete (OC1) is employed. The findings contribute to the understanding of optimal shielding configurations required to mitigate neutron radiation from IECF devices. Ensuring adherence to regulatory safety standards is paramount in the deployment of these fusion devices within populated areas. This research underscores the importance of selecting appropriate materials and thicknesses to achieve effective radiation protection, thereby facilitating the safe operation of IECF devices and contributing to advancements in medical isotope production and neutron-based interrogation technologies.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1790523</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1790523</link>
        <title><![CDATA[Advanced modeling and management strategies for nuclear and radiological incidents: from decision support to adaptive governance]]></title>
        <pubdate>2026-03-13T00:00:00Z</pubdate>
        <category>Review</category>
        <author>Petre Cornel Min</author>
        <description><![CDATA[Nuclear and radiological emergency preparedness and response (EPR) including decision-support systems and emergency management frameworks operate at the intersection of advanced technical modelling, organizational processes, human decision-making, and societal dynamics. This review is based on a critical synthesis of the scientific and institutional literature addressing dispersion modelling, decision-support systems, emergency management frameworks, and large-scale exercise practice in nuclear and radiological emergencies. By examining how modelling outputs are generated, interpreted, and operationalized across preparedness and response contexts, the review identifies persistent gaps between analytical capabilities and real-world decision-making under uncertainty, time pressure, and multi-actor coordination. The analysis reveals that while significant progress has been achieved in modelling and computational tools, their integration into adaptive management and governance structures remains limited. Existing decision-support approaches often emphasize predefined scenarios and procedural compliance, offering limited support for exploratory reasoning and trade-off analysis in complex and evolving emergencies. Building on these findings, the review advances the concept of Hybrid Emergency Operations Centers (Hybrid EOCs) as an integrative operational and governance framework that connects modelling, decision-support, organizational workflows, and human-in-the-loop decision-making. Rather than prescribing optimal decisions, the proposed approach positions advanced modelling to structure decision spaces, enhance transparency, and support adaptive judgement within complex emergency response ecosystems.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1787346</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1787346</link>
        <title><![CDATA[Identification of safety-relevant radionuclides for performance assessment modeling]]></title>
        <pubdate>2026-03-09T00:00:00Z</pubdate>
        <category>Original Research</category>
        <author>Stefan Finsterle</author><author>Michael J. Hannon</author><author>Jesse Sloane</author>
        <description><![CDATA[We propose, apply, and verify a screening approach for the selection of safety-relevant radionuclides that should be tracked in models assessing the performance of geologic repositories for the disposal of spent nuclear fuel and high-level radioactive wastes. Starting with a comprehensive list of radionuclides present in the waste form, a multi-step down-selection process evaluates each isotope’s potential relative contribution to the total peak exposure dose, which is a surrogate metric for overall repository safety. In the first screening step, only basic, readily available characteristics of a radionuclide are needed, such as its inventory, half-life, specific activity, and dose coefficient. In the second step, the radionuclide’s transport time from the repository to the accessible environment is estimated based on factors affecting its mobility and retardation. By adjusting the screening threshold, the number of radionuclides considered potentially safety-relevant can be changed, thus yielding a larger or smaller (more or less conservative) set of radioisotopes being tracked in the performance assessment model, as warranted by the stage of repository development. We exercise the proposed screening approach for a particular waste form—spent nuclear fuel assemblies—and two disposal pathways—deep horizontal and vertical borehole repositories. An integrated performance assessment model is then used to simulate the migration of a considerably larger set of radionuclides from the disposal canisters to the land surface. The acceptably small difference in peak dose calculated with the comprehensive and reduced set of radionuclides indicates the appropriateness of the proposed screening approach.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2025.1765005</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2025.1765005</link>
        <title><![CDATA[Editorial: EURAD: state of the art in research and development on radioactive waste management and disposal]]></title>
        <pubdate>2026-02-25T00:00:00Z</pubdate>
        <category>Editorial</category>
        <author>Tara Beattie</author><author>Bernd Grambow</author>
        <description></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1714531</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1714531</link>
        <title><![CDATA[Evaluation of the Lawson criterion for aneutronic proton-boron-11 fusion: effects of ion temperature and bremsstrahlung losses]]></title>
        <pubdate>2026-02-24T00:00:00Z</pubdate>
        <category>Original Research</category>
        <author>Irfan Maulana Ahmad</author><author>Abd. Djamil Husin</author><author>Duong Thanh Tai</author><author>Nissren Tamam</author><author>Abdelmoneim Sulieman</author><author>Sitti Yani</author>
        <description><![CDATA[Nuclear fusion, the process of combining light nuclei to form heavier nuclei, offers a promising pathway to sustainable clean energy with minimal radioactive waste. The Lawson criterion, expressed as the product of plasma density, confinement time, and temperature, establishes the conditions required for ignition and net energy gain. This study investigates the Lawson criterion for proton-boron-11 (p-11B) fusion across ion temperatures of 75–500 keV, incorporating fusion reactivity data from Tentori-Belloni and Nevins-Swain, as well as energy losses from bremsstrahlung radiation under different electron-to-ion temperature ratios (TeTi= 1, 0.5, 0.25). The Tentori-Belloni dataset yields higher fusion reactivity than Nevins-Swain, resulting in more favorable Lawson values. Net energy production is achieved only when Te<Ti, with optimal operating windows identified at 190–330 keV for Te= 0.5Ti and 125–500 keV for Te= 0.25Ti. At Ti< 230 keV, the Lawson criterion decreases due to plasma instabilities and confinement limitations; in this work, radiative losses are evaluated using Zeff=2.4 derived from the p-11B fuel mixture (npnB=90:10) only, while external impurity contributions are not explicitly modeled. For Ti> 230 keV, the Lawson criterion increases, reaching characteristic minima around 330 keV and 500 keV. These thresholds represent the minimum conditions required to achieve ignition and sustain a self-sufficient fusion reaction. The minimum Lawson values obtained were 1.3 × 1022 m−3s (no radiation), 1.2 × 1023 m−3s (Te= 0.5Ti), and 1.5 × 1022 m−3s (Te= 0.25Ti). These findings highlight the critical role of accurate cross-section data and electron-ion temperature control in advancing aneutronic p-11B fusion toward practical, self-sustained clean energy systems.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1795642</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1795642</link>
        <title><![CDATA[A future design approach to nuclear waste repository siting: activating futurability and cultivating pride]]></title>
        <pubdate>2026-02-19T00:00:00Z</pubdate>
        <category>Perspective</category>
        <author>Tatsuyoshi Saijo</author>
        <description><![CDATA[Nuclear waste repository siting presents an unprecedented intergenerational challenge: decisions made today will affect approximately 5,000 future generations over 100,000 years. Contemporary approaches in Finland, Sweden, and France rely almost exclusively on present-generation perspectives in societal decision-making. While achieving varying degrees of local acceptance through institutional trust and economic compensation, these processes implement no systematic exercises where current residents adopt future generations’ temporal viewpoints. Future Design (FD) offers a complementary framework by activating futurability—the capacity to experience present happiness through pursuing future generations’ wellbeing. FD employs dual perspective-taking: temporal (through integrated Past Design, Present Design, and Future Design exercises) and spatial (host-beneficiary dialogue). This cultivates three forms of pride: achievement pride from confronting civilization’s waste challenge, collective pride in community contribution, and anticipatory pride imagining descendants’ evaluation. Unlike compensation-based acceptance, pride-based acceptance emerges intrinsically through perspective-taking. Rigorous pilot testing comparing FD and non-FD deliberations is essential, with ethical safeguards ensuring transparency and genuine openness to rejection. Integrating FD into repository siting can help demonstrate what current generations owe future generations: not merely engineered safety, but proven concern.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2025.1738676</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2025.1738676</link>
        <title><![CDATA[First evaluation of geopolymer encapsulation of simulated alkaline aluminum-rich liquid waste from Mo-99 production]]></title>
        <pubdate>2026-02-11T00:00:00Z</pubdate>
        <category>Original Research</category>
        <author>Whitney Talavera Ramos</author><author>Adrián Tellería Narváez</author><author>Lucas Dos Santos</author><author>Daniel Arcone</author><author>Ayelén Manzini</author>
        <description><![CDATA[This study investigates the synthesis and characterization of metakaolin-based geopolymers for the immobilization of simulated aluminum-containing radioactive liquid waste. Two kaolin precursors with different Si/Al ratios and purities were calcined between 700 °C and 900 °C. Geopolymers were prepared using a sodium silicate–NaOH activating solution (10 M NaOH) with and without sand, and cured at 60 °C. The effects of curing time and simulated liquid waste incorporation (10–40 wt%) on mechanical strength and microstructural development were evaluated through compressive strength tests, XRD, and SEM analyses. The results showed that curing time influenced strength development. Incorporation of simulated liquid waste generally reduced compressive strength, probably due to increased porosity and decreased metakaolin (MK) dissolution; however acceptable performance was achieved at a 20 wt% addition for MKSR-based geopolymers. XRD analyses confirmed the formation of an amorphous band between 25° and 35° typical of geopolymer structures. In contrast, MKS-based geopolymers exhibited lower mechanical strength and incomplete gel formation under the tested conditions. These findings demonstrate the potential of local precursor MKSR metakaolin-based geopolymers as promising matrices for the immobilization of aluminum-bearing radioactive liquid waste.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2025.1720142</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2025.1720142</link>
        <title><![CDATA[High-fidelity multi-physics guidelines for model validation and uncertainty quantification]]></title>
        <pubdate>2026-02-04T00:00:00Z</pubdate>
        <category>Original Research</category>
        <author>Gregory K. Delipei</author><author>Quentin Faure</author><author>Maria Avramova</author><author>Kostadin Ivanov</author>
        <description><![CDATA[The verification, validation, and uncertainty quantification (VVUQ) of high-fidelity, high-resolution multi-physics modeling and simulation in nuclear engineering applications are essential for assessing the predictive credibility of developed models. Appropriate practices and methods are required to address ongoing challenges. Some key examples include the large dimensionality of the input and output spaces, modeling complexity, high computational cost, scarcity of relevant experimental data, and the lack of guidelines and protocols for the development of multi-physics benchmarks. This study provides several guidelines and recommendations. Dimensionality reduction and screening approaches can be used to address the high-dimensional input and output spaces. A multi-level validation hierarchy where the coupling level is increased progressively is suggested to manage modeling complexity. A validation scoring method is proposed to compare the different coupling levels and to identify gaps in the modeling. Surrogate models can be used to address the computational cost, though they require the estimation of an additional model uncertainty. For consistent uncertainty propagation, sample-processing diagrams are introduced that can help avoid sampling errors between the multiple inputs. For the validation of multivariate outputs such as time series, local, regional, and global univariate metrics can be used together with more complicated multivariate methods based on U-pooling. Some of the proposed recommendations are demonstrated on the multi-physics modeling of the first cold ramp test from the OECD/Nuclear Energy Agency (NEA) Multi-physics Pellet Cladding Mechanical Interaction Validation (MPCMIV) benchmark. The multi-level modeling hierarchy ranges from single-physics fuel performance models to coupled multi-physics models. The MOOSE-based tools Griffin, Bison, and THM are employed alongside the fuel performance code OFFBEAT. The measurements considered in here include the cladding’s axial elongation and coolant temperature at three different locations during the cold ramp test. Validation metrics are computed at local, regional, and global scales. Validation scores are computed for each model and physics domain. The results highlight the need for at least a coupling between the RP and FP to accurately predict the cladding axial elongation, whereas the coolant temperatures are less sensitive to the coupling level due to their small variations during the cold ramp test.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2025.1694684</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2025.1694684</link>
        <title><![CDATA[Accelerating the engineering design of breeder blankets with parametric optimisation and sequential learning]]></title>
        <pubdate>2026-02-02T00:00:00Z</pubdate>
        <category>Original Research</category>
        <author>Luke Humphrey</author><author>Helen Brooks</author><author>Siddharth Mungale</author><author>Andrew Davis</author><author>David Foster</author>
        <description><![CDATA[The competing requirements of fusion breeder blankets and the high dimensionality of their design space necessitate a systematic treatment to map the variations in performance against given objective metrics and to understand the operational envelope. In this endeavour, a digital engineering pipeline for design evaluation and optimisation has been developed. The tools involved are Hypnos for parametric breeder blanket geometry instantiation, OpenMC for neutronics analysis, MOOSE for thermal hydraulics analysis, and SLEDO for design space sampling, sensitivity analysis, and optimisation. An optimisation of the baseline design for a solid ceramic breeder mock-up that is relevant to the Lithium Breeding Tritium Innovation (LIBRTI) program is performed. Two optimisation studies are performed, the first involving only neutronics, while the second includes the impact of thermal hydraulics. The figures of merit are taken to be the tritium breeding ratio (TBR) and the pressure drop of the outer coolant (combined in a weighted sum for the second analysis). In the first study, for the same acquisition function (taken to be expected improvement), two different values are selected for the hyperparameter that controls the trade-off between exploration and exploitation. In the second study, with the inclusion of thermal hydraulics, a larger parameter space was explored to assess the performance of the method in a higher dimensionality setting. In both cases, the selected figures of merit were improved over the baseline design. Finally, we discuss extensions of the procedure to include a more thorough multi-physics analysis and a more sophisticated treatment of multiple objectives.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1762086</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1762086</link>
        <title><![CDATA[Pebble dynamics and thermal-fluid analysis of high-temperature gas-cooled pebble bed reactors using DEM and CFD simulations]]></title>
        <pubdate>2026-01-30T00:00:00Z</pubdate>
        <category>Original Research</category>
        <author>Kashminder S. Mehta</author><author>Braden Goddard</author><author>Zeyun Wu</author>
        <description><![CDATA[This study presents a multiphysics computational simulation framework for analyzing pebble dynamics and thermal-fluid behavior in High-Temperature Gas-Cooled Pebble Bed Reactors (HTG-PBR). The pebble circulation and intermixing effects are predicted using Discrete Element Method (DEM) implemented in LIGGGHTS, while the thermal-fluid behavior is simulated with computational fluid dynamics (CFD) in OpenFOAM. The CFD model employs a porous-media formulation with a local thermal non-equilibrium model to capture the energy exchange between the helium coolant and pebbles. Integrating the DEM-based mixing effects into the porous CFD model enables a more physically representative and scalable approach for full-core reactor analysis. Both DEM and CFD solvers are validated using established pebble-bed benchmark problems to confirm the viability of the developed computational models. A HTG-PBR-like conical model reactor is employed as a test problem to evaluate the developed method. The simulation results confirm the predictive capability of the developed models for HTG-PBR performance analysis and provide insight for future multiphysics coupling strategies for reactor design optimization.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2025.1736818</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2025.1736818</link>
        <title><![CDATA[Adsorption of Pb(II) and brilliant green dye onto geopolymer/zeolite hybrid composites]]></title>
        <pubdate>2026-01-09T00:00:00Z</pubdate>
        <category>Original Research</category>
        <author>Hammad R. Khalid</author>
        <description><![CDATA[Geopolymers, aluminosilicate materials formed by alkali activation, have drawn interest because of their unique mechanical, chemical, and thermal characteristics. They are interesting for adsorption applications due to their similar chemical structure to zeolite. This study investigates the synthesis and characterization of hybrid geopolymer/zeolite composites to remove lead ions (Pb(II)) and brilliant green (BG) dye from aqueous solutions. Sodium hydroxide and sodium silicate were used to activate fly ash and blast furnace slag blends. This was followed by hydrothermal treatment to encourage the conversion of amorphous geopolymeric gel to crystalline zeolites. Several variables were systematically changed, such as foaming agents, alkali molarity, and bead size to compare adsorption performance. The formation of zeolite phases was confirmed by structural and morphological investigations, such as XRD, FT-IR, SEM, and BET, which also shed light on the porous character of the composite. The geopolymer/zeolite composites demonstrated notable removal efficiency for Pb(II) (up to 123 mg/g) and BG dye (up to 115 mg/g) in adsorption studies. Importantly, this work reveals that average pore diameter plays a more critical role than surface area in determining adsorption capacity of bulk-type adsorbents, contrasting conventional assumptions in the field. The work provides possibilities for creating long-lasting, efficient adsorbents for the treatment of water by highlighting the roles that pore size and surface area play in the adsorption mechanism. Given the structural similarity between heavy metals and certain radionuclides, these findings have broader implications for developing geopolymer-based materials for radioactive waste treatment applications.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2025.1714098</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2025.1714098</link>
        <title><![CDATA[An ensemble data-driven method for fault detection and diagnosis of digital control systems in nuclear power plants]]></title>
        <pubdate>2026-01-08T00:00:00Z</pubdate>
        <category>Original Research</category>
        <author>Baimao Lei</author><author>Bohao Tian</author><author>Yingrong Yao</author><author>Chenyu Jiang</author><author>Jun Yang</author>
        <description><![CDATA[Fault detection and diagnosis (FDD) is essential for maintaining safety and preventing hazardous situations in industrial process control. Effective fault diagnosis allows for the timely detection and correction of anomalies, preventing potential disruptions and maintaining optimal performance. In the paper, we present a unified framework for fault detection and diagnosis by combining the real-time sensitivity of the moving window particle filtering (PF) with the diagnostic precision of the generalized likelihood ratio test (GLRT). Within the framework, the particle filtering is integrated to provide accurate real-time state monitoring and prediction in scenarios with nonlinear digital control system dynamics and non-Gaussian noise. The moving window (MW) is adopted to identify anomalous patterns within a stream of data by focusing on a fixed-size segment that moves across the data. The GLRT is then used to isolate the specific type of fault that has occurred based on the observed data and the different fault hypotheses and models. The method is demonstrated with a digital U-shaped tube steam generator water level control system in pressurized water reactor nuclear power plants. Comparative studies have also been conducted with LSTM network to demonstrate the effectiveness and superiority of the proposed PF-based MW-GLRT method. The demonstration results show that the proposed PF-based MW-GLRT framework can provide a robust and efficient solution for identifying and characterizing faults in complex digital control systems.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2025.1729916</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2025.1729916</link>
        <title><![CDATA[Modeling glass degradation and release of radionuclides from vitrified waste for performance assessment simulations]]></title>
        <pubdate>2026-01-05T00:00:00Z</pubdate>
        <category>Original Research</category>
        <author>Stefan Finsterle</author><author>Jeffrey R. McLachlan</author><author>Michael J. Hannon</author><author>Jesse Sloane</author><author>Rebecca J. Abergel</author><author>Per F. Peterson</author>
        <description><![CDATA[The release of radionuclides initially encapsulated in a slowly degrading solid waste form and contained in an eventually corroding canister defines the source term for numerical simulations for the assessment of a geologic repository for high-level radioactive waste. While the details of waste degradation, canister corrosion, and dissolution and mobilization of the radionuclides in pore water include complex chemical reaction and transport processes that are coupled to the thermal, hydrological, microbiological, and mechanical conditions in the repository, the source-term model suitable for use in a numerical performance assessment model should be a defensible abstraction of these mechanisms. We developed a radiological source-term model and implemented it into a non-isothermal flow and transport simulator. While the proposed source-term model is applicable to various waste forms, canister systems, and disposal concepts, we specifically considered radionuclide releases from vitrified high-level waste placed in a cylindrical canister disposed in a deep vertical borehole repository. In this model, waste degradation is a function of temperature, and it can be adjusted to evaluate the influence of and propagate uncertainties in pH, passivation reactions, and chemical conditions as well as geometrical factors. The time-dependent, congruent release of safety-relevant radionuclides present in the decaying inventory is then calculated. Finally, the radionuclides are mobilized by diffusive and advective transport according to the thermo-hydraulic conditions prevailing in the near field of the repository, from where they migrate through the geosphere to the accessible environment. We examine the influence of the source-term model’s parameters on performance assessment calculations through sensitivity and uncertainty propagation analyses, identifying influential factors and confirming the upper bound of their impact. These considerations align with the overarching goal of repository design, which is to demonstrate that engineered and natural barriers can collectively delay radionuclide migration for timescales far exceeding human planning, thereby providing multiple, redundant barriers against environmental contamination.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2025.1751259</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2025.1751259</link>
        <title><![CDATA[Correction: Editorial: Multiphysics methods and analysis applied to nuclear reactor systems]]></title>
        <pubdate>2025-12-17T00:00:00Z</pubdate>
        <category>Correction</category>
        <author>Mark D. DeHart</author><author>Emily Shemon</author><author>Deokjung Lee</author>
        <description></description>
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