<?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>2026-10-24T17:27:13.114+00:00</pubDate>
        <ttl>60</ttl>
        <item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1971830</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1971830</link>
        <title><![CDATA[Small modular reactors for data centers: deployment and nuclear fuel requirements]]></title>
        <pubdate>2026-10-22T00:00:00Z</pubdate>
        <category>Original Research</category>
        <author>Willian Vieira de Abreu</author><author>Aquilino Senra Martinez</author><author>Artur Souza e Silva</author><author>Leonardo Kenji Takashi</author><author>Álefe Calebe Ribeiro Lima</author><author>Júlia de Barros Bordin de Pontes</author><author>Luis Lionel Salas Ramon</author><author>Alessandro da Cruz Gonçalves</author><author>Adilson Costa da Silva</author><author>Fernando Carvalho da Silva</author><author>Marco Antonio C. Lima</author>
        <description><![CDATA[This paper evaluates the deployment and potential nuclear fuel requirements of Small Modular Reactors (SMR) for supplying the electricity demand associated with data center expansion. The proposed approach is applied to Brazil as a reference scenario, for which an original database was developed based on Ministerial Ordinances issued by the Brazilian Ministry of Mines and Energy (MME) between 2020 and 2025 regarding requests to connect data center facilities to the National Interconnected System (SIN). From this survey, a reference electricity demand scenario of approximately 2.52 GW was constructed, concentrated mainly in the states of São Paulo and Ceará. Three Pressurized Water Reactor (PWR)-type SMR designs were comparatively evaluated using reactor core modeling and fuel-cycle-based metrics, including Initial Heavy Metal Mass (IHMM), burnup, and natural uranium requirements. The evaluated reactors were the ACP100, BANDI, and RITM-200N. The analysis combines OpenMC-based reactor inventory estimations with fuel utilization models to estimate the required number of reactor units and fleet-level uranium demand associated with SMR deployment. The results indicate significant differences among reactor designs regarding deployment scale, fuel inventory, and uranium consumption. The RITM-200N presented the lowest IHMM requirement, whereas its higher enrichment level resulted in the largest specific natural uranium demand per unit of electricity generated. Overall, the study provides a physically grounded framework for evaluating the deployment and material implications of SMR for data center electricity supply, which can be adapted to alternative demand scenarios as more precise or context-specific data become available.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.2001814</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.2001814</link>
        <title><![CDATA[Correction: Better physics, less noise: inline multi-physics reduces correlation in Monte Carlo reactor simulations]]></title>
        <pubdate>2026-10-16T00:00:00Z</pubdate>
        <category>Correction</category>
        <author>Frontiers Production Office </author>
        <description></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1894792</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1894792</link>
        <title><![CDATA[Additive manufacturing of nuclear materials under irradiation extremes: thermal-mechanical performance, qualification challenges, and future research directions]]></title>
        <pubdate>2026-10-13T00:00:00Z</pubdate>
        <category>Review</category>
        <author>Irfan Nazir Wani</author>
        <description><![CDATA[This review examines additive manufacturing (AM) of nuclear materials. Three core advantages of AM for nuclear reactor components are identified: high geometric complexity, short lead times, and tunable microstructures. Five mainstream AM technologies are reviewed: laser powder bed fusion (LPBF), directed energy deposition (DED), electron beam powder bed fusion (EB-PBF), wire arc additive manufacturing (WAAM), and binder jetting. Focusing on four material classes (austenitic and ferritic-martensitic steels, oxide dispersion-strengthened (ODS) alloys, refractory metals and plasma-facing materials, and silicon carbide composites), the review establishes process–structure–property–performance (PSPP) relationships. The core emphasis is on thermomechanical behavior under extreme operating conditions: temperatures up to 1,000 °C (Generation IV reactors), transient heat fluxes exceeding 10 MW m-2 (fusion devices), and neutron irradiation up to 200 displacements per atom (dpa). AM-specific irradiation failure mechanisms are analyzed. Four critical unresolved problems are identified: (i) thermal stability of AM-specific dislocation structures under service conditions, (ii) conflicting reports on irradiation swelling resistance between AM and wrought alloys, (iii) absence of standardized qualification pathways, and (iv) limited neutron irradiation data, with existing data restricted to doses below 10 dpa. Finally, the review highlights knowledge gaps concerning synergistic effects among irradiation, corrosion, and thermomechanical loading and proposes prioritized directions for future research.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1845169</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1845169</link>
        <title><![CDATA[The safety case for a deep geological repository in Switzerland: system evolution and performance assessment]]></title>
        <pubdate>2026-10-09T00:00:00Z</pubdate>
        <category>Original Research</category>
        <author>Alexandros Papafotiou</author><author>Typhaine Guillemot</author><author>Lukas Martin</author><author>Nikitas Diomidis</author><author>Paul Marschall</author>
        <description><![CDATA[The post-closure safety case for a deep geological repository requires a transparent and traceable demonstration that the repository system fulfils its safety functions and remains robust against uncertainties over relevant timescales. This paper presents the performance assessment workflow implemented in the context of the safety case for a general license application of a deep geological repository for both high-level waste (HLW) and low- and intermediate-level waste (L/ILW) at the Haberstal site in Switzerland. The safety concept relies on a staggered system of passive and redundant barriers, the so-called multibarrier system, each performing specified safety functions in the general post-closure safety architecture. The performance assessment addresses the performance of each component of the multibarrier system, as well as the overall performance of the total system, building upon claims, arguments, and evidence in a transparent and traceable manner. Rigorous handling of uncertainty is an indispensable element in this assessment workflow. The uncertainty framework aims to bracket the confidence bounds on the expected system response evaluated through the simplified model representations of the repository system and the internal or external perturbations acting on it. The possible paths of repository performance are formulated into an expected performance and safety-relevant deviations thereof, assessed in a probabilistic framework with an indicator-based approach. Their safety relevance and likelihood of occurrence form the main input for the development of safety scenarios, which is the next step in the safety assessment workflow. The analysis demonstrates a robust performance of the geological repository through a redundant barrier system that fulfils the intended safety functions under both expected repository performance and deviations from it. The presented methodology provides a transparent and systematic framework for evaluating performance in support of the safety case. The assessment integrates quantitative indicator-based analyses, management of uncertainty, and evidencing of argumentation, contributing to confidence building in the long-term safety of the Swiss deep geological repository.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1843948</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1843948</link>
        <title><![CDATA[The safety case for a deep geological repository in Switzerland: radiological consequence analysis and study of the barrier efficiency]]></title>
        <pubdate>2026-10-09T00:00:00Z</pubdate>
        <category>Original Research</category>
        <author>Xiaoshuo Li</author>
        <description><![CDATA[Geological repositories for radioactive waste are sited and designed to provide a set of natural and engineered barriers that isolate the waste from the human environment and contain its associated radionuclides. Nonetheless, some release of radionuclides from a geological repository cannot be excluded over the Time frame of hundreds of thousands of years during which the waste presents a potential hazard. Thus, radiological consequence analysis is a key element of the post-closure safety case for deep geological repositories and provides essential insight into the efficiency of the multi-barrier system. This paper presents the current methodology and selected results of the radiological consequence analysis for a combined repository for high-level waste and low- and intermediate-level waste in an Opalinus Clay rock formation hundreds of metres below ground at a proposed site in Northern Switzerland. Deterministic and probabilistic simulations are performed to evaluate radionuclide transport, barrier efficiency, and associated uncertainties. Radionuclide migration in the liquid phase is modelled for a wide range of potentially safety-relevant radionuclides, while gas-phase transport focuses on C-14 released as methane under two-phase flow conditions. Results show that calculated dose rates are several orders of magnitude below Swiss regulatory protection criterion, demonstrating a large safety margin. Long-lived, weakly sorbing radionuclides, particularly I-129, dominate the calculated dose in a reference safety scenario that corresponds to the expected evolution of the repository and in a range of other scenarios, while most other radionuclides are effectively retained within the engineered barriers and the Opalinus Clay host rock. Probabilistic analyses and sensitivity studies identify key parameters controlling radionuclide release. Overall, the analysis confirms the robustness of the multi-barrier system and provides improved understanding of the Swiss deep geological repository system.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1921592</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1921592</link>
        <title><![CDATA[Better physics, less noise: inline multi-physics reduces correlation in Monte Carlo reactor simulations]]></title>
        <pubdate>2026-09-17T00:00:00Z</pubdate>
        <category>Original Research</category>
        <author>P. Cosgrove</author>
        <description><![CDATA[Recently, several authors have proposed that multi-physics calculations involving coupled neutronics and thermal-hydraulics are most efficiently performed using tight or ‘inline’ coupling. This consists of passing neutronic information to the thermal-hydraulics solver before the neutronics solution is fully converged, providing benefits in stability and runtime. In the context of Monte Carlo neutronics, this work considers the effects of correlation on the results of these calculations by varying both the frequency of data exchanges and the neutron population used each cycle. This is done using newly developed multi-physics capabilities in the Monte Carlo code SCONE. The results show that inline coupling throughout the entire Monte Carlo calculation is not only robust to the choice of neutron population, but also reduces the inter-generational correlation between neutrons, producing lower variance results than if the coupled physics fields were not updated. For the 3D pin problem considered, this implies about 2.89× fewer active particles can be simulated in a coupled calculation to achieve the same power errors as an uncoupled calculation using the correct temperature and density fields.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1966757</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1966757</link>
        <title><![CDATA[Editorial: Advanced modeling and management strategies for nuclear and radiological incidents]]></title>
        <pubdate>2026-09-09T00:00:00Z</pubdate>
        <category>Editorial</category>
        <author>Nadja Zeleznik</author>
        <description></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1860013</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1860013</link>
        <title><![CDATA[Plan alignment and operational interfaces in nuclear security event response: evidence from Türkiye’s all-hazards emergency management system]]></title>
        <pubdate>2026-09-01T00:00:00Z</pubdate>
        <category>Original Research</category>
        <author>Zeyneb Camtakan</author><author>Didem Saloglu</author>
        <description><![CDATA[Nuclear security event response within all-hazards systems requires coordination among emergency management, regulatory, law enforcement, technical and forensic actors operating under distinct mandates. This study examines how nuclear security event response is specified within Türkiye’s national emergency management system. Based on structured documentary analysis of publicly available planning, regulatory, strategic and review documents, the study applies the Four C framework to assess communication, coordination, collaboration, and cooperation across institutional interfaces. The findings show that Türkiye’s planning architecture provides a coordinated basis for radiological emergency response. However, nuclear security events are less clearly specified as a distinct response problem. Partially specified interfaces include command transition, forensic evidence management, security-sensitive information sharing, detection-to-response activation, and international notification timing. The study does not assess operational performance or classified capabilities. It provides a case-based diagnostic of how formal plan alignment may not translate into clearly specified operational response arrangements when nuclear security events require emergency management, regulatory, law enforcement, technical, and forensic functions to operate simultaneously.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1900800</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1900800</link>
        <title><![CDATA[LEACS: lagrange error-adaptive collision sampling for multiphysics coupled Monte carlo transport]]></title>
        <pubdate>2026-08-31T00:00:00Z</pubdate>
        <category>Original Research</category>
        <author>W. Reed Kendrick</author><author>Benoit Forget</author>
        <description><![CDATA[In tightly coupled multiphysics simulations, the conventional Monte Carlo assumption of piecewise-constant material properties is no longer valid, as temperature and density fields vary continuously in space. Current approaches to this problem each impose limitations on accuracy, generality, or computational efficiency. This work introduces the Lagrange Error-Adaptive Collision Sampling (LEACS) method, which addresses spatially varying material properties during Monte Carlo neutron transport by dynamically evaluating the coupled finite element solution along the particle’s flight path. Rather than converting the multiphysics solution into a lower-order representation, LEACS accesses native element shape functions directly, with sample positions chosen analytically via the Lagrange error bound to optimally minimize error in the reconstructed collision probability distribution. LEACS is implemented in OpenMC and demonstrated on pin cell and assembly test cases and coupled with MOOSE thermal solutions. Analytical error analysis confirms that Lagrange-adaptive spacing consistently outperforms equidistant spacing, with the greatest gains observed for long axial flight paths. Spatial tally results suggest that as few as three sample points per flight segment are sufficient to capture the radial and axial impact of temperature gradients on the (n,γ) reaction rate distribution. Computational cost analysis reveals slowdown factors vary depending on the model geometry, with finite element point location and inverse mapping as the dominant cost components and primary targets for future optimization.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1884654</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1884654</link>
        <title><![CDATA[Application and validation of a higher-fidelity architecture for coupled neutronic and thermal-hydraulic analysis in the XE-prime nuclear thermal propulsion system]]></title>
        <pubdate>2026-08-31T00:00:00Z</pubdate>
        <category>Original Research</category>
        <author>Jonathon Thomsen</author><author>Camden Eck</author><author>Dan Kotlyar</author>
        <description><![CDATA[Development of a nuclear thermal propulsion (NTP) engine is pursued by government and industry. Current deployment regulations require that experimental efforts are heavily complemented and guided by modeling and simulation. Challenges arise when directly simulating the physics of such systems at steady-state operation and especially during transients due to strongly coupled local and global effects. Reduced-order methods are commonly used as a practical means for obtaining full-core solutions, however these methods must be verified against higher-fidelity solvers. Therefore, a Python package, ANTHMM, has been developed that is intended for general usability and allows users to externally couple Monte Carlo neutronics solvers and commercial CFD software. In its current state, ANTHMM is optimized for the Serpent Monte Carlo code and Ansys Fluent CFD. Using published data from the XE-Prime NTP engine, a CFD model has been generated, validated, and used as a reference model for a fully coupled reduced-order solver. The CFD model and reduced order solver show excellent agreement for the hot-condition test data in three different regions of the core, which were recorded during the XE-Prime experiment. The neutronic behavior predicted by the fully coupled reduced order solver is very similar to that predicted by the coupled CFD model. Finally, it is shown that informed prediction from a reduced order solver of first-iteration temperatures and densities used in the MC simulation can reduce the coupled simulation from several iterations to a single predictor-corrector step.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1921673</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1921673</link>
        <title><![CDATA[Meaningful dose in geological disposal safety cases: human intrusion and normal evolution as competing exposure pathways]]></title>
        <pubdate>2026-08-24T00:00:00Z</pubdate>
        <category>Hypothesis and Theory</category>
        <author>Claudio Pescatore</author>
        <description><![CDATA[Geological disposal safety assessments distinguish normal evolution from inadvertent human intrusion. Normal evolution is treated as the expected long-term behaviour of the disposal system; human intrusion is treated as a stylised future human action whose probability cannot be forecast reliably over geological timescales. This distinction is justified, but it can obscure a protection-relevant question: which pathway is more likely to produce a meaningful dose over a specified assessment period? This paper proposes comparing both pathways through P(D ≥ D*), the probability that a pathway produces a dose equal to or greater than a specified meaningful-dose threshold. The central claim is architectural: normal-evolution compliance, cumulative boundary-bypass probability, conditional consequence after physical intersection, and likelihood of meaningful dose are distinct quantities that should not be collapsed into a single plausibility judgement. The Finnish TURVA-2012 review illustrates the issue: human intrusion was the only disturbance scenario producing dose within the 10,000-year window. Normal evolution is the most fully modelled pathway, but the repository’s engineered and geochemical barriers are designed to suppress corresponding exposure. Human intrusion is less predictable, but once waste or contaminated material is physically intersected, it may be more exposure-efficient because it can bypass the attenuation sequence on which normal-evolution safety depends. A safety case may therefore be complete as a compliance demonstration while remaining incomplete as a protection claim. This note addresses that architectural gap by reframing human intrusion and normal evolution as competing pathways to meaningful dose.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1878296</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1878296</link>
        <title><![CDATA[Citizen measurement of ambient dose rate: challenges and opportunities]]></title>
        <pubdate>2026-08-19T00:00:00Z</pubdate>
        <category>Review</category>
        <author>Jean-Marc Bertho</author>
        <description><![CDATA[Radiation measurements by citizen appeared for the first time in the aftermath of the Chornobyl accident and received a renewed interest in the aftermath of the Fukushima accident. At that time, several networks of citizen measurement of radioactivity appeared in Europe, mainly acting for education to radioactivity and the science of measurement and for education, both initial and continuous, to risks associated to radioactivity. However, these networks suffer from a lack of sustainability due to several parameters, including lack of long-term funding, lack of credibility of citizen-led data and lack of applications in data use. This review identifies and details challenges that these networks have to face with, and opportunities they can use to increase the useability of citizen measurement data.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1893691</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1893691</link>
        <title><![CDATA[Securing cloud-enabled radiation detection systems: a risk-informed cybersecurity framework for nuclear sensor networks]]></title>
        <pubdate>2026-08-04T00:00:00Z</pubdate>
        <category>Perspective</category>
        <author>Nelson Kodzotse Agbemava</author><author>Etornam Ann Mensah</author><author>Kwame Appiah</author><author>Christopher M. Spirito</author>
        <description><![CDATA[Cloud computing is increasingly being adopted in nuclear and radiological monitoring systems to address the limitations of traditional on-premises infrastructures. Radiation Detection Systems (RDS), which rely on distributed sensor networks, generate large volumes of data requiring scalable storage, real-time processing, and secure transmission. While cloud integration enhances flexibility, mobility, and cost efficiency, it introduces significant cybersecurity challenges, particularly in high-consequence nuclear environments. This conceptual study evaluates the integration of cloud computing architectures with nuclear sensor networks and proposes a risk-informed cybersecurity framework tailored for cloud-enabled RDS, using a structured STRIDE threat-to-layer mapping and a qualitative likelihood-impact risk scoring exercise grounded in documented case studies. Key enabling technologies, including Sensor Cloud architectures, Everything-as-a-Service (XaaS), and multi-tenancy models, are examined alongside the Shared Responsibility Model governing cloud security. Threat scenarios such as supply chain compromise, advanced persistent threats, and cyber-physical attacks are analyzed using real-world case studies, including Operation Cloud Hopper and the Triton incident. This analysis indicates that cloud platforms enhance scalability, data availability, and disaster recovery capabilities, but introduce risks related to reduced system visibility, expanded attack surfaces, and dependency on third-party service providers, with supply-chain compromise and sensor-data falsification emerging as the highest-priority risks under the qualitative scoring applied here. A layered cybersecurity framework aligned with IAEA Nuclear Security Series guidance and international cybersecurity standards is proposed, addressing data protection in transit, at rest, and during processing. This study suggests that cloud computing may be securely adopted in nuclear sensor networks when supported by robust governance, regulatory alignment, and risk-informed cybersecurity controls; this conclusion is conceptual and desk-based, and would require expert validation, simulation, or pilot deployment before being treated as an operational recommendation.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1783403</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1783403</link>
        <title><![CDATA[Neutronics model developments for the IFMIF-DONES test cell]]></title>
        <pubdate>2026-07-30T00:00:00Z</pubdate>
        <category>Original Research</category>
        <author>Yuefeng Qiu</author><author>Arkady Serikov</author><author>Irene Alvarez</author><author>Fernando Mota</author><author>Aljaž Čufar</author><author>Santiago Becerril</author><author>Jesus Castellanos</author>
        <description><![CDATA[This work presents the development and evolution of the test cell (TC) neutronics geometry models for IFMIF-DONES (International Fusion Materials Irradiation Facility–Demo Oriented Neutron Source), supporting detailed Monte Carlo–based nuclear analyses for design assessment and optimization. Beginning with the IFMIF/EVEDA configuration, successive model versions have been developed to reflect major DONES design updates, including the design changes to a single accelerator and test module, revised target assembly (TA) and High Flux Test Module (HFTM) designs, relocation of the quench tank, and the introduction of removable biological shielding blocks (RBSBs). To balance modeling accuracy and computational efficiency, both high-fidelity and lightweight geometry representations were investigated. Sensitivity studies on geometry boundaries and levels of simplification demonstrate that key irradiation performance metrics, such as neutron flux and damage doses, are well preserved when essential TA and HFTM features are retained. Simplified yet representative target and HFTM models were validated for use in accelerated simulations. In parallel, an unstructured mesh-based HFTM model was successfully implemented and benchmarked against conventional CSG-based models, showing excellent agreement.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1779804</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1779804</link>
        <title><![CDATA[Multiphysics methods for species tracking in molten salt reactors]]></title>
        <pubdate>2026-07-22T00:00:00Z</pubdate>
        <category>Original Research</category>
        <author>Samuel A. Walker</author><author>Mauricio Tano</author><author>Parikshit Bajpai</author><author>Abdalla Abou-Jaoude</author>
        <description><![CDATA[Recent advancements in nuclear energy, particularly in the development of Molten Salt Reactors (MSRs), emphasize a shift towards integrating advanced technology for enhanced safety and efficiency. MSRs utilize unique fuel cycles and offer significant advantages over traditional reactors, including flexibility in fuel utilization and improved safety mechanisms. This study introduces a multiphysics species tracking framework developed within the Multiphysics Object-Oriented Simulation Environment (MOOSE), designed to model the intricate behaviors of species within MSR systems. The framework integrates neutron transport, thermal-hydraulics, and thermochemical dynamics, allowing for the analysis of species transport phenomena, including leaching, plating, and corrosion. The framework was applied to a generic Molten Salt Fast Reactor (MSFR) model, revealing critical insights into temperature-driven material leaching and plating processes. It demonstrated how temperature gradients and redox potential changes significantly influence the behavior of corrosion products, with specific concentrations tracked over time. Notably, the introduction of beryllium as a redox control measure was shown to mitigate corrosion by reducing the redox potential of the fuel salt. The findings underscore the importance of species tracking in MSRs for reactor safety, design optimization, and regulatory compliance. This research not only elucidates the dynamic interactions between various species in molten salt systems but also highlights the framework’s potential to guide future developments in MSR technology. The results indicate a clear pathway for enhancing reactor design and operational safety through informed modeling, paving the way for advanced nuclear reactor deployment in the near future. Future work will focus on validation against experimental data and further refinement of the framework to support ongoing advancements in MSR technology.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1861381</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1861381</link>
        <title><![CDATA[Research on the stratification characteristics of binary inert gas mixture]]></title>
        <pubdate>2026-07-17T00:00:00Z</pubdate>
        <category>Original Research</category>
        <author>Xiang Shi</author><author>Zhouyang Xu</author><author>Fulong Zhao</author><author>Shuo Wang</author><author>Ruifeng Tian</author><author>Sichao Tan</author>
        <description><![CDATA[Gas-cooled reactors are among the most promising Generation IV nuclear energy systems, and helium-based binary mixtures are attractive candidate coolants because of their favorable thermophysical and chemical properties. In this work, a numerical investigation was conducted to study the distribution evolution and thermal stratification of a He–Ar gas mixture in a closed cylindrical vessel. The effects of the mixing ratio, initial pressure, vessel aspect ratio, initial temperature, and axial temperature difference on the species distribution were systematically analyzed. The results indicate that the mixing ratio, initial pressure, vessel aspect ratio, and initial temperature exert only minor effects on the overall gas distribution. By contrast, the axial temperature difference is identified as the key factor controlling the onset and intensity of stratification. A larger temperature gradient induces stronger compositional non-uniformity and results in more pronounced axial stratification within the vessel. In addition, temperature non-uniformity further amplifies the stratification process. These results provide a quantitative basis for evaluating composition non-uniformity in closed gas systems. The present study improves the mechanistic understanding of coupled thermal and compositional stratification in confined binary rare-gas mixtures and provides a reference for evaluating similar transport phenomena in gas-cooled nuclear systems.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1843718</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1843718</link>
        <title><![CDATA[The safety case for a deep geological repository in Switzerland: development of safety scenarios]]></title>
        <pubdate>2026-07-16T00:00:00Z</pubdate>
        <category>Methods</category>
        <author>Hoda Javanmard</author>
        <description><![CDATA[This paper presents Nagra’s systematic methodology for developing safety scenarios for the post-closure safety case in support of the Swiss general licence application for deep geological disposal of radioactive waste. The approach builds on the assessment basis, performance assessment outcomes, and international guidelines. It combines top-down safety-function reasoning with bottom-up FEP screening to ensure comprehensive and traceable coverage of system evolutions. Four safety scenario categories are defined: the reference safety scenario describing expected evolution, alternative safety scenarios addressing credible deviations, hypothetical “what-if?” cases testing system robustness, and stylised safety scenarios of future human actions. Each scenario is complemented by variants and calculation cases designed to capture conceptual and parametric uncertainties relevant for post-closure safety. The resulting scenario set provides a structured and manageable input for radiological consequence analyses and confidently bounds the radiological consequences of a comprehensive range of plausible and hypothetical evolutions. Through conservative assumptions, bounding variants, and structured safety scenario categorisation, the methodology robustly supports the demonstration of post-closure safety and ensures regulatory compliance. The work establishes a defensible and scientifically grounded safety scenario framework that underpins the post-closure safety assessment for deep geological disposal in Switzerland.]]></description>
      </item><item>
        <guid isPermaLink="true">https://www.frontiersin.org/articles/10.3389/fnuen.2026.1868886</guid>
        <link>https://www.frontiersin.org/articles/10.3389/fnuen.2026.1868886</link>
        <title><![CDATA[Thermodynamics for radiation-induced segregation and phase change needed]]></title>
        <pubdate>2026-07-09T00:00:00Z</pubdate>
        <category>Opinion</category>
        <author>Reza Darvishi Kamachali</author>
        <description></description>
      </item><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>
      </channel>
    </rss>