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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>
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        <pubDate>2026-07-07T15:49:22.23+00:00</pubDate>
        <ttl>60</ttl>
        <item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1822290</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1822290</link>
        <title><![CDATA[Full-core high-burnup BWR LOCA fuel performance analysis and FFRD susceptibility]]></title>
        <pubdate>2026-06-24T00:00:00Z</pubdate>
        <category>Original Research</category>
        <author>Ian Greenquist</author><author>Aaron Wysocki</author><author>Pierre-Clément A. Simon</author><author>Ryan Sweet</author><author>Kyle Gamble</author><author>Mehdi Asgari</author><author>Asher Hansen</author><author>Baris Sarikaya</author><author>Ian Porter</author><author>James Tusar</author><author>Nathan Capps</author><author>Robert Salko</author>
        <description><![CDATA[The susceptibility of the boiling water reactor (BWR) Limerick Unit 1 to fuel fragmentation, relocation, and dispersal during a postulated large-break loss-of-coolant accident (LBLOCA) was calculated using a multiphysics framework. The simulations include full-core, rod-resolved neutronic, thermal hydraulic, and fuel performance models using the VERA, TRACE, and BISON codes. This work focused on the transient BISON simulations, which include both the normal operation and LBLOCA periods in the same simulations. Cladding integrity was assessed using two correlations that are included with BISON. make page break Several new BWR-specific features were recently added to BISON. This work represents the first time these features have been included in a core-scale set of simulations. This study hence evaluates the performance of these new models for an operating reactor with realistic operating conditions. Simulation results showed that cladding integrity was maintained (i.e., no rods burst). Finally, future work to improve BWR and PWR predictions using this framework is suggested.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1758465</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1758465</link>
        <title><![CDATA[On the feasibility of fissile material production with inertial electrostatic confinement fusion devices]]></title>
        <pubdate>2026-06-19T00:00:00Z</pubdate>
        <category>Hypothesis and Theory</category>
        <author>Alex Little</author><author>Yannick Verbelen</author><author>Mahmoud Bakr Arby</author><author>Thomas B. Scott</author>
        <description><![CDATA[Inertial electrostatic confinement fusion devices (fusors) are becoming increasingly attractive neutron sources, and are well suited for global distribution with great humanitarian benefits. However, such neutrons are agnostic to the user’s intent, so could in theory be used for malicious means. This paper discusses the feasibility of using fusors to convert fertile thorium-232 or uranium-238 into fissile material for the purpose of proliferating a nuclear weapon, and whether this is a simple, convenient, and subtle method compared to existing means such as nuclear piles or enrichment plants. Such an effort would require one or more fusors to produce in excess of 1016 neutrons per second. This neutron production rate is out of range of contemporary device technologies, and would be drastically inferior to conventional proliferation techniques. Without significant breakthroughs in fusor technology, this paradigm is expected to remain.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1843726</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1843726</link>
        <title><![CDATA[The safety case for a deep geological repository in Switzerland: engineered barriers for low- and intermediate-level waste disposal]]></title>
        <pubdate>2026-06-18T00:00:00Z</pubdate>
        <category>Review</category>
        <author>Lukas Martin</author><author>Georg Kosakowski</author><author>Typhaine Guillemot</author><author>Alexandros Papafotiou</author>
        <description><![CDATA[The safe geological disposal of low- and intermediate-level radioactive waste relies on a passive multi-barrier system. This paper presents the provisional Swiss design for the low- and intermediate-level waste (L/ILW) emplacement caverns and their expected evolution. In the current design, containers are stacked within the L/ILW disposal caverns, and the remaining void space is backfilled with a porous mortar. Because cementitious materials are used in large quantities, they largely determine the geochemical conditions in the L/ILW near field. A key property of these cementitious materials is their ability to maintain a high-pH porewater environment. Such conditions limit the degradation of organic materials and suppress microbial activity. They also promote the passivation of metal surfaces, resulting in slow corrosion rates and consequently reduced gas generation. The chemical evolution of the near field is strongly coupled to the repository’s saturation history, as water is required for chemical reactions such as for the corrosion of metals, degradation of organic matter or pozzolanic reactions. Given the low permeability of Opalinus Clay, water availability in the caverns is limited, and partially saturated conditions are expected to persist for several hundreds of thousands of years. These conditions help maintain elevated pH levels, particularly in the unsaturated regions of the emplacement caverns. The substantial presence of cementitious materials also enhances the retention and slow release of radionuclides from the L/ILW near field into the host rock, once the waste packages breach. As a result, the L/ILW near field contributes to key safety functions, including immobilization, retention, and controlled release of radionuclides, as well as ensuring compatibility among repository components. The properties and long-term behaviour of these components are sufficiently well understood to allow a robust description of their evolution over extended timescales, supporting the demonstration of their barrier function and long-term performance.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1849685</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1849685</link>
        <title><![CDATA[The safety case for a deep geological repository in Switzerland: site and geological barrier characteristics]]></title>
        <pubdate>2026-06-18T00:00:00Z</pubdate>
        <category>Review</category>
        <author>Raphael A. J. Wüst</author><author>Michael Schnellmann</author><author>Angela Landgraf</author><author>Silvio Giger</author><author>Nicolas Roy</author><author>Daniel Traber</author><author>Gaudenz Deplazes</author><author>Raphael Schneeberger</author><author>Jens K. Becker</author><author>Nathan Looser</author><author>Urs H. Fischer</author><author>Valentina Zampetti</author><author>Tim Vietor</author>
        <description><![CDATA[Deep geological repositories for radioactive waste rely on geological barriers to isolate waste and impede or limit radionuclide migration over long geological timescales or until radioactivity has decreased to natural radiation levels. This study summarises the main geological evidence and arguments for the containment-providing rock zone (CRZ), including the host rock Opalinus Clay, as effective geological barriers for Switzerland’s deep geological repository. The information and data are part of Nagra’s comprehensive safety case within the framework of the general licence application. The geological assessment basis contains an integrated multi-scale site characterisation, covering data from 3D-seismic investigations and nine deep boreholes from the latest exploration campaign. Highlights of the geological data include: 1) high-resolution 3D-seismic datasets that image the subsurface structure, including undisturbed structural domains, key stratigraphic horizons, and the geometry of faults; 2) a comprehensive field and laboratory dataset that demonstrates that the hydraulic conductivities of the Opalinus Clay and remaining CRZ units are extremely low, that solute transport is diffusion-dominated, and that key properties have high vertical and lateral continuity; 3) independent natural-tracer profiles that developed over millions of years and confirm slow, diffusion-dominated transport across the CRZ; 4) a laboratory-derived mechanistic understanding and field evidence of self-sealing processes in the Opalinus Clay that show that fracture transmissivities decrease relatively rapidly after mechanical perturbation; 5) a systematic abstraction approach that groups geological units with similar properties and provides a modelling framework for evaluating safety- and performance-relevant processes; and 6) broad-ranging evidence that demonstrates the long-term geological stability of the Opalinus Clay with respect to the expected tectonic, geomorphological and hydrological changes during glacial-interglacial cycles over the next one million years. The synthesis presented here demonstrates how the geological data and its abstraction provide a robust and internally consistent basis for the safety assessment supporting the Swiss general licence application.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1842834</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1842834</link>
        <title><![CDATA[The safety case for a deep geological repository in Switzerland: engineered barriers for high-level waste disposal]]></title>
        <pubdate>2026-06-12T00:00:00Z</pubdate>
        <category>Review</category>
        <author>Nikitas Diomidis</author><author>Typhaine Guillemot</author><author>Lukas Martin</author><author>Alexandros Papafotiou</author><author>Olivier X. Leupin</author>
        <description><![CDATA[The safe geological disposal of high-level radioactive waste requires a passive multi-barrier system. This paper describes the engineered barriers foreseen in the provisional Swiss repository concept, covering both design aspects as well as evidence for their long-term performance. Disposal canisters made of carbon steel will be used for the encapsulation of spent nuclear fuel and vitrified high-level waste. The canisters are designed to corrode slowly and predictably in the repository as well as to withstand external mechanical loads, leading to long lifetimes. The bentonite buffer surrounding the canisters, upon saturation with water, will swell and provide a stable environment around the high-level waste disposal canisters, limiting corrosion, inhibiting microbial activity, and ensuring an even distribution of mechanical loads. Furthermore, after the breaching of the canisters and the release of radionuclides, the buffer ensures diffusion-dominated transport and promotes sorption and immobilisation by precipitation. In addition, a compacted bentonite sealing element seals the drift and limits water flow along the repository components. The properties of these components are understood well enough to allow an adequate description of their evolution over long time-scales, thus allowing to demonstrate their barrier function and long-term performance.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1854910</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1854910</link>
        <title><![CDATA[Neutronic and safety evaluation of a hybrid UO2-U3Si2 accident tolerant fuel assembly for VVER-1000 reactors]]></title>
        <pubdate>2026-06-11T00:00:00Z</pubdate>
        <category>Original Research</category>
        <author>S. M. Saidur Rahman Turjak</author>
        <description><![CDATA[This paper evaluates the neutronic feasibility and multi-physics safety of a hybrid Accident Tolerant Fuel (ATF) assembly in a VVER-1000 reactor. The proposed design strategically employs standard UO2 within the inner core and a high-density U3Si2 matrix in the peripheral pins to take advantage of inter-assembly thermalization for cycle length extension. Coupled evaluations were performed using OpenMC continuous-energy Monte Carlo transport and OpenFOAM steady-state conjugate heat transfer Computational Fluid Dynamics (CFD). The hybrid assembly meets the target of extending the depletion cycle to 540 days through the rapid breeding of peripheral Pu-239. Although this configuration induces intensely localized radial power peaking (399.18 W/cm3), the superior metallic thermal conductivity of U3Si2 (>15.0 W/m⋅K) completely eliminates the thermal penalty. OpenFOAM simulations of the ATF pins demonstrate that the peak centerline temperatures are reduced by 50 K compared to the interior of the UO2 core (690 K vs. 740 K), yielding a drastic reduction in localized sensible stored energy. Neutronic safety is strictly preserved, maintaining deeply negative Fuel and Moderator Temperature Coefficients (−1.895 pcm/K and −36.533 pcm/K) alongside a robust B4C Control Rod Worth (65,323.56 pcm). These results demonstrate that the hybrid ATF assembly fundamentally improves LOCA coping times while enhancing the overall economics of the reactor.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1857667</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1857667</link>
        <title><![CDATA[RADRISK Inspector: a mobile application for shielding design and safety distance calculation in industrial gamma radiography]]></title>
        <pubdate>2026-06-10T00:00:00Z</pubdate>
        <category>Original Research</category>
        <author>M. Suffo</author><author>D. Brea-Piñero</author><author>J. F. Molina-Pérez</author><author>J. M. Mota-Macías</author>
        <description><![CDATA[Industrial gamma radiography is a widely used non-destructive testing (NDT) technique, but it involves significant radiological risks that require precise planning of shielding and safety distances. Current practices rely heavily on in-situ radiometric measurements, which are time-consuming and may increase unnecessary operator exposure during setup and verification stages. This work presents RADRISK Inspector (RRI), a cross-platform mobile application that enables real-time radiological safety planning through physics-based calculations. The system estimates minimum safety distances, required shielding thickness, and risk zoning based on radionuclide activity, exposure parameters, and material attenuation properties. In addition, RRI integrates interactive zoning maps, exposure timers, and automated dosimetric reporting compliant with international standards (IAEA, CSN), supporting full digitalization of radiological risk management workflows. The application was preliminarily verified under real industrial conditions during pipeline weld inspections using an Ir-192 source. In this field case, RRI estimated an operator safety distance of 66 m, compared with 22 m obtained from in-situ dose-rate measurements, indicating conservative behaviour consistent with its safety-first planning approach. Accordingly, RRI is not intended to replace in-situ radiometric verification or high-fidelity radiation transport modelling, but to support conservative pre-inspection planning, risk zoning and traceable professional reporting in industrial gamma radiography. RRI represents a novel and beneficial application of radioactivity in modern industry, enabling proactive radiological protection, reducing unnecessary exposure, and improving operational efficiency in gamma radiography. Its compatibility with ATEX-certified devices further supports deployment in hazardous environments. This work supports a shift in radiographic NDT from reactive measurement-based practices to predictive, physics-based safety planning.]]></description>
      </item><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>
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