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EDITORIAL article

Front. Nucl. Eng.

Sec. Nuclear Reactor Design

Volume 4 - 2025 | doi: 10.3389/fnuen.2025.1717262

This article is part of the Research TopicMultiphysics Methods and Analysis Applied to Nuclear Reactor SystemsView all 10 articles

Editorial: Multiphysics Methods and Analysis Applied to Nuclear Reactor Systems

Provisionally accepted
  • 1Abilene Christian University, Abilene, United States
  • 2Argonne National Laboratory, Lemont, United States
  • 3Korea Advanced Institute of Science and Technology, Daejeon, Republic of Korea

The final, formatted version of the article will be published soon.

Traditional nuclear engineering has relied heavily on experimentation, often involving costly and potentially hazardous procedures. Multiphysics simulations provide a robust framework for reactor experiment and full system evaluation. By integrating models that accurately represent the inherent coupling of physical phenomena: neutronics, thermal hydraulics, structural mechanics, heat transfer, etc., these simulations oFer a complete view of reactor behavior under a wide set of conditions. This unified approach enables designers and analysts to optimize designs, predict performance, and enhance safety in ways previously unattainable.With the wide variety of reactor types on the horizon, advanced multiphysics modeling and simulation oFers clear advantages of the use of traditional physics codes and workflows. Generally, the tightly coupled nature of multiphysics methods allows for more flexible code application and deeper physics insights than what can be obtained with loosely or one-way coupled tools. This is especially important for exploring the technical merits of novel reactor concepts with less experimental pedigree. This collection highlights contributions that showcase the breadth and depth of multiphysics applications in nuclear engineering. From innovative computational methods to rigorous experimental validation, the articles presented here underscore the critical role that simulation plays in representing the complexities of modern nuclear reactor technology.A notable advancement within this domain is described in Imron and Lee through the development of on-the-fly thermal expansion methodologies for multiphysics Monte Carlo reactor simulations as This method allows the problem geometry to dynamically expand during particle tracking by incorporating local temperature data, such as pin-averaged temperatures obtained from thermal-hydraulics solvers. Numerical experiments demonstrate that modeling thermal expansion with local temperature data can significantly improve the accuracy of simulations, including eigenvalue predictions and pin power distributions, compared to models using only global core-averaged temperatures A central theme emerging from this Research Topic is the development and application of innovative computational methods. For instance, Harter and DeHart details the application of stochastic methods and sensitivity analysis to a full-core model of a nuclear thermal propulsion system. This research showcases the development of a reduced-order model that allows for rapid evaluation of system behavior under various input conditions, a critical advancement for optimizing the design and control of these complex reactors.The integration and coupling of diFerent physical models is another area of focus. Advanced nuclear reactor cores are governed by multiple physical phenomena which should all be resolved, and the coupling of these physics would also need to be resolved spatially in a high-fidelity approach. Giudicelli et al. presents field transfer capabilities implemented in the Multiphysics Object-Oriented Simulation Environment (MOOSE), and numerous technical details such as mapping heuristics, conservation techniques and parallel algorithms. In a similar vein, Yang et al. explores hybrid, matrix-based, and matrixfree solver technologies within a voxel-dominated Cartesian mesh framework, oFering a novel approach to simulating neutronics and thermal hydraulics in nuclear reactor cores. This approach enables accurate boundary representation and eFicient resolution of complex geometries. The coupling of diFerent physical models, such as neutronics and thermal hydraulics, is crucial for accurate reactor analysis.The application of these advanced simulations extends to design optimization, with several articles demonstrating how multiphysics models can inform and refine reactor designs. presents the development of a multiphysics coupled framework of Kim, Oh and Kim, which provides significant insights into the analysis of MSRs. Zavala et al. discusses a high-detail steady-state analysis of one VVR-KN fuel assembly. The VVR-KN is a plate-type fuel assembly, with fuel elements arranged hexagonal with fuel-plate tubes that challenges both their neutronic and thermal-hydraulic modeling. The paper describes the thermalhydraulic code Subchanflow and how the properties are solved and provided.The collection also emphasizes the role of multiphysics simulations in safety analysis. Kutlu et al. highlights the continuous development and improvement of the CTF subchannel tool for thermal hydraulics, including new functionalities and multiphysics applications for VVER core modeling. These advancements are critical for ensuring the safe and reliable operation of these reactor types.A cornerstone of credible simulation is rigorous experimental validation. Colvin and Palmer compares simulations to experimental results from the Sanida Annular Core Research Reactor, exploring potential improvements for feedback purposes, allowing additional iterations of the multiphysics coupling and checking for convergence, and evaluation of uncertainties in provided specific heat capacity values. These validation eForts are essential for establishing confidence in the predictive capabilities of multiphysics models.Kendrick and Forget presents coupled neutronic/thermal-mechanical simulation of the Kilowatt Reactor Using Stirling TechnologY (KRUSTY) using OpenMC and MOOSE in order to analyze the neutronic and thermal impact of including thermal expansion at steady state. The results show that while thermal expansion has a significant eFect on global neutronic tallies, it has relatively minor impact on spatial heating rates or temperatures in the system. This remains true even when simulating a multiple heat pipe failure scenario to introduce thermal asymmetry.Looking ahead, the continued advancement and application of multiphysics methods hold significant promise for the future of nuclear energy modeling and design. By fostering collaboration between industry, academia, and research laboratories, and by prioritizing rigorous validation and uncertainty quantification, the nuclear community can unlock the full potential of these powerful simulation tools. This Research Topic serves as a valuable resource for researchers, engineers, and regulatory personnel alike, providing a comprehensive overview of the state-of-the-art and paving the way for a safer, more eFicient, and more sustainable nuclear future.This collection provides evidence to the significant impact of multiphysics simulation capabilities in nuclear engineering. By including these advanced techniques, the nuclear industry can work to address the challenges of advanced reactor concepts.

Keywords: Multiphysics modeling, Nuclear reactor systems, simulation, thermal hydraulics, Safety analysis, modeling, Neutron transport

Received: 01 Oct 2025; Accepted: 13 Oct 2025.

Copyright: © 2025 DeHart, Shemon and Lee. This is an open-access article distributed under the terms of the Creative Commons Attribution License (CC BY). The use, distribution or reproduction in other forums is permitted, provided the original author(s) or licensor are credited and that the original publication in this journal is cited, in accordance with accepted academic practice. No use, distribution or reproduction is permitted which does not comply with these terms.

* Correspondence: Mark D. DeHart, mdd25c@acu.edu

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