<?xml version="1.0" encoding="utf-8"?>
    <rss version="2.0">
      <channel xmlns:content="http://purl.org/rss/1.0/modules/content/">
        <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>2026-06-03T17:52:11.276+00:00</pubDate>
        <ttl>60</ttl>
        <item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1840800</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1840800</link>
        <title><![CDATA[The safety case for a deep geological repository in Switzerland: assessment and modelling of the biosphere]]></title>
        <pubdate>2026-06-01T00:00:00Z</pubdate>
        <category>Methods</category>
        <author>Ashley Brown</author><author>Raphael A. J. Wüst</author><author>Russell Walke</author><author>Rebecca Newson</author><author>Louise Bruffell</author><author>Valentyn Bykov</author><author>Priska A. Hunkeler</author><author>Angela Landgraf</author><author>Urs H. Fischer</author><author>Jens K. Becker</author><author>Michael Schnellmann</author>
        <description><![CDATA[The post-closure biosphere assessment and modelling in support of the general licence application for a deep geological repository for radioactive waste provides the basis for evaluating radiological consequences should radionuclides released from the geological repository reach the surface and near-surface environments. The assessment approach comprises the modelling of radionuclide migration in the biosphere following potential releases from the geosphere to a local aquifer over timescales of tens of thousands to more than a million years. A stylised approach is adopted, including reference and alternative biosphere conditions, consistent with both national and international regulations and guidelines. The model is implemented in Nagra’s SwiBAC code, which allows radionuclide fluxes to the biosphere to be translated into potential doses to humans. This process yields equilibrium biosphere dose conversion factors (BDCFs) for each radionuclide for use in the analysis of radiological consequences, which occurs in a separate assessment step. Reference biosphere calculations are based on present-day conditions in Northern Switzerland, represented by a valley setting with a temperate climate. These conditions support a wide range of potential radionuclide transport and exposure pathways, including agricultural water use, soil-plant transfer, and local food consumption. Three alternative biospheres are also assessed to address uncertainties in long-term climate and geomorphology, including (i) a warmer-drier climate, where aquifer and surface flows are reduced while irrigation is increased, (ii) a cold climate with permafrost, where the exchange between soil and the aquifer is reduced, and (iii) a drained farmland setting with a high water table. BDCFs vary significantly between these cases, increasing by up to about an order of magnitude in warmer-drier conditions and decreasing by up to about five orders of magnitude under cold-climate conditions. These results highlight the key role of the shallow aquifer and transfer pathways within the valley agriculture system. Deterministic and probabilistic sensitivity analyses further highlight the influence of sorption in the shallow aquifer, hydrological fluxes, and agricultural transfer pathways. Together, the reference and alternative cases constrain key uncertainties and provide a robust, conservative basis for evaluating long-term radiological safety.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1840901</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1840901</link>
        <title><![CDATA[The safety case for a deep geological repository in Switzerland: concepts for waste disposal and methodology for safety assessment]]></title>
        <pubdate>2026-05-15T00:00:00Z</pubdate>
        <category>Methods</category>
        <author>Paul Smith</author>
        <description><![CDATA[This paper describes the deep geological repository concept considered by Nagra in support of its recent general licence application and the methodology used by Nagra to demonstrate its post-closure safety. The concept presented is for a deep geological repository for high-level waste (HLW) and for low- and intermediate-level waste (L/ILW) located in the Opalinus Clay host rock in Switzerland. The safety and repository concept is based on geological and engineered barriers which together perform a range of different high-level safety functions. The safety case is built on an assessment basis that is defined as the evidence, knowledge, assessment tools, and methodologies developed or acquired in support of the safety assessment. The safety assessment itself consists of four main steps or processes: i) performance assessment, in which arguments are developed and evidence presented to show that the safety functions of the repository are upheld and that the system will evolve as expected in most reasonably foreseeable situations, ii) safety scenario development, which defines a set of safety scenarios that capture alternative ways in which the repository system could evolve over time, taking uncertainty into account, iii) the analysis of radiological consequences, which uses quantitative models to evaluate annual individual dose rates or risks for these safety scenarios and compares the results with regulatory guidelines, and iv) the demonstration of post-closure safety, which synthesises the various lines of argument and evidence to produce the safety case. The paper provides an overview of the safety assessment methodology. Detailed aspects of performance assessment, safety scenarios development and the analysis of radiological consequences are provided in separate papers within this special issue.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1837826</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1837826</link>
        <title><![CDATA[Rethinking Germany’s energy transition: a role for nuclear power to meet climate targets and keep economic competitiveness]]></title>
        <pubdate>2026-05-14T00:00:00Z</pubdate>
        <category>Perspective</category>
        <author>Friedbert Pflüger</author>
        <description><![CDATA[Germany's nuclear phase-out is being increasingly questioned due to rising electricity demand, geopolitical insecurity, and industrial competitiveness concerns. In no small part, the rethinking comes from a growing recognition that, although renewable energy remains central to climate neutrality, Germany's renewable-heavy energy transition is insufficient to meet climate targets. In addition to the role of hydrogen-ready gas power plants and renewables, this paper argues that Germany ought to consider the role that new generations of nuclear energy, particularly Small Modular Reactors (SMR), can play in phasing-out coal and meeting future electricity demand. As global interest in new generations of nuclear reactors is rising, Germany's economic, climate and energy policy would benefit from engaging in this momentum and taking advantage of its public's recently easing attitudes towards nuclear energy. The paper concludes with ten policy recommendations that position nuclear energy as a complement to renewables and low-carbon gases, especially in a geopolitical context where diversification is more critical than ever.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1776967</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1776967</link>
        <title><![CDATA[Enhancing fast neutron irradiation in thermal neutron spectrum reactors through python-based multi-objective optimization]]></title>
        <pubdate>2026-05-08T00:00:00Z</pubdate>
        <category>Original Research</category>
        <author>Mustafa K. Jaradat</author><author>Jason V. Brookman</author><author>Andrew Bascom</author><author>Tommy Holschuh</author><author>Nicolas E. Woolstenhulme</author>
        <description><![CDATA[This work reports on a pilot study for optimizing the design of a fast neutron irradiation experiment in a thermal neutron spectrum, specifically the Advanced Test Reactor (ATR). A fast and robust multi-objective optimization workflow that leverages Python-based open-source tools was developed and applied to the ATR to optimize experiment design and boost fast energy neutrons at a desired irradiation location. Three design options were explored to minimize thermal and epithermal neutron flux, deposited heat, and total estimated cost while maximizing the absolute fast neutron flux. This was achieved by considering several irradiation positions in the ATR with different combinations and thicknesses of filter and booster materials. The developed workflow utilizes high-fidelity Monte Carlo calculations to train a surrogate model of each objective function being optimized, thereby reducing computational efforts while searching for the optimized set of solutions. The results show that absolute fast neutron flux increased approximately 30% to 55% in regions with a harder spectrum, while the absolute fast neutron flux increased significantly by 7 to 10 times in regions with a softer spectrum outside the core but still lower than the regions with harder spectrum. Also, The predictions of the surrogate models were verified against the high-fidelity Monte Carlo calculations, and these tests showed that the surrogate models made accurate predictions.]]></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.2026.1760157</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.2026.1771702</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>
      </channel>
    </rss>