The European Journal of Physics N (EPJ-N)
Not a member yet
448 research outputs found
Sort by
Current capabilities and future developments of Monte Carlo code MCS
No full textThe Monte Carlo code, MCS was developed at the Ulsan National Institute of Science and Technology (UNIST) in 2011. In the initial development phase, the primary focus was on developing a Monte Carlo code for the high-fidelity multicycle analysis of large-scale power reactors, especially pressurized water reactors. For the power reactor analysis, capabilities including refueling and shuffling of fuel assemblies, on-the-fly Doppler broadening of neutron cross-sections, and multiphysics coupling were implemented in the MCS. Beyond reactor analysis and capabilities, MCS has been developed to extend its applications. The MCS has been used for radiation shielding, group constants generation, sensitivity, uncertainty, and transient analysis. This study provides a general overview of MCS capabilities
Review of JAEA’s Monte Carlo codes for nuclear reactor core analysis
No full textJapan Atomic Energy Agency (JAEA) has been developing a general-purpose continuous-energy Monte Carlo code MVP for nuclear reactor core analysis. Recently improvements to MVP have been focused on the development of an advanced neutronics/thermal-hydraulics coupling code. JAEA has also developed a new Monte Carlo solver Solomon for criticality safety analysis. Solomon aims to calculate the criticality of fuel debris. This paper provides an overview of the capabilities and reviews recent applications of MVP and Solomon
Study of radiolysis bubbles in bitumen used for nuclear waste management with ultrasounds and X-Ray microtomography
No full textIn the realm of nuclear waste management, an ultrasonic investigation of radiolysis bubbles in bitumen has been carried out. Mechanical waves are very sensitive to gas cavities in matter, therefore ultrasonic velocity was measured in a straight-run distillation bitumen labelled AZALT 70/100 irradiated with 60Co (gamma irradiation) at dose rates between 5 and 1200 Gy/h and total integrated doses ranging from 2 to 100 kGy in IRMA and PAGURE French irradiation facilities. A comparative study of ultrasonic velocity and X-Ray microtomography measurements shows that ultrasonic velocity is linked to the concentration of bubbles within the material. A first attempt to deduce the volume fraction of hydrogen bubbles created by irradiation at ambient conditions with ultrasonic velocity measurements are proposed and discussed. This method constitutes an interesting approach dedicated to the monitoring of radiolysis bubbles formation and their evacuation mechanisms. It is particularly promising as ultrasonic sensors can operate effectively in high radiative and high temperature environments. Thus, real time application can be envisaged during irradiation and temperature increase for future experiments
Equilibrium state core calculations for an SCW-SMR concept using the Apros-SPNDYN coupled code system
No full textThe Institute of Nuclear Techniques of the Budapest University of Technology and Economics is actively involved in the development of a supercritical water-cooled small modular reactor concept as a consortium member within the ECC-SMART project, which received an EU/EURATOM/H2020 grant in 2020. For coupled thermal hydraulics and reactor physics analysis of this reactor concept, the SPNDYN in-house finite element reactor physics code has been coupled to the Apros thermal hydraulics system code, using a Transmission Control Protocol/Internet Protocol-based communication method within a Python environment. After introducing the supercritical water-cooled small modular reactor concept under development, this paper presents the methodology used for coupling Apros and SPNDYN, detailing the developed system code and reactor physics models, as well as sensitivity analyses related to the models. The results of coupled equilibrium state calculations performed with the Apros-SPNDYN code system for two different core layouts at the beginning of cycle reactor state are then presented. One of the core loading patterns suggested for the first cycle of the supercritical water-cooled small modular reactor consists of solely 5.0 at.% U235 enriched fuel assemblies, while the other is an optimised pattern with three differently enriched UO2 assemblies. The obtained results are compared to reference Apros-Serpent 2 calculations for verification purposes. By coupling Apros and SPNDYN, coupled reactor physics and thermal hydraulics analyses of various transient scenarios of the core concept under development become possible with future contribution to a more thorough safety evaluation of this pre-conceptual design. This paper relates to the application of the SPNDYN finite element reactor physics code developed within the framework of the PhD research conducted by B. Babcsány and shortlisted for the PhD Award of the High Scientific Council of the European Nuclear Society in 2024
Extending Embedded Monte Carlo as a novel method for nuclear data uncertainty quantification
No full textThe purpose of this paper is to introduce a new approach to compute nuclear data uncertainties called Embedded Monte Carlo (EMC) and compare it to the well-established Total Monte Carlo (TMC) method. While the TMC methodology involves generating numerous random nuclear data library samples and conducting separate Monte Carlo simulations for each, this approach calculates nuclear data uncertainties by subtracting statistical uncertainties from the total uncertainties of each simulation. The EMC method addresses the challenge of statistical uncertainty where each batch represents a new random sample, thereby embedding the propagation of uncertainties within a single calculation and reducing computational costs. This technique also enables the calculation of nuclear data uncertainties by leveraging a combination of history and batch statistics in eigenvalue calculations. This paper demonstrates the potential of the EMC method using OpenMC with an analysis performed on two different benchmarks by propagating the uncertainty on three input parameters: the average neutron multiplicity
, the prompt neutron fission spectrum (PFNS) χ and the 239Pu density
Earthquake precursor measurements employing a network of radon sensors
No full textEarthquakes, as one of the most prominent natural disasters, pose a severe threat to societies in regions near active fault lines. Being able to forecast when, where and how strong an earthquake will be is beyond current scientific capabilities. At present, forecasting methods yield earthquake occurrence probabilities within a specific time frame spanning several years. Measurements of changes of radon concentrations in groundwater have shown pronounced changes preceding imminent earthquakes. The potential in using radon as a precursor for earthquakes has been explored by multiple groups over many years. Radon measurements in soil have shown large variations in activity, partly due to atmospheric influences. The ArtEmis project seeks to offer new insight into the correlation between imminent earthquakes and changes in radon emission from the upper crust by employing novel concepts for measurements and analysis. The paper presents system aspects of the ArtEmis project, a description of the ArtEmis sensor prototype and first results
Coordination of the European Research Community on Nuclear Materials for Energy Innovation: the research agenda of the CONNECT-NM co-funded European partnership
No full textCONNECT-NM is a recently launched co-funded European partnership that deals specifically with boosting innovation in the field of nuclear materials. It pursues five research lines, dedicated to: (1) knowledge and data management; (2) advanced materials development and manufacturing; (3) materials and component qualification (testing, standardization and design rules); (4) non-destructive examination and materials health monitoring; (5) advanced materials modelling and characterization. The present paper details the methodology and the scientific and technical expected results for each of these research lines, in pursuit of the corresponding five nuclear materials-dedicated end-products, respectively: knowledge organisation system, materials acceleration platforms and advanced manufacturing processes, qualification test-beds and accelerated qualification paths, intelligent materials health monitoring and advanced predictive methodologies. The work to be performed in connection with prioritization of research activities, education and training, access to infrastructures, communication, dissemination and results exploitation is also discussed, together with the expected impact
Main goals and research outcomes of the EU Projects ELSMOR, McSAFER, and EASI-SMR: regulatory, experimental and analytical safety-related investigations
No full textSmall modular reactors are being developed globally with first new builds being planned within a decade. The most near-term designs are based on light water reactor technologies. While the fundamental technology is well known, the designs aim to utilize passive safety functions and simplifies systems to drive down costs. The correct operation of these functions must be ensured for these new nuclear reactors to be licensed in Europe. This paper discusses three projects funded by Euratom Research and Training programme: ELSMOR, McSAFER, and EASI-SMR.
In this paper, the main goals and selected outcomes of two European research projects that finished some months ago will be presented and discussed. In addition, the main goals and the research program of the EASI-SMR project will be described
Towards improvement of the operation and safety of European nuclear power plants through enhanced thermal-hydraulics experiments and analysis
No full textDue to the negligible levels of CO2 it produces, nuclear energy is gaining a more prominent role in the current transition to clean energy. An important aspect to nuclear energy generation is the safety of nuclear installations. To ensure safe operation of nuclear reactors, all facets must be carefully monitored and controlled, and the behavior of the operational and safety systems must be assessed in detail under normal and off-normal conditions. A key aspect herein is the reactor thermal-hydraulics, crucial to ensure heat generated in the core gets transferred to the secondary system, during electricity generation, or designated heat sinks, for emergency scenarios. Two European projects focusing on reactor thermal-hydraulics recently received grants within the Euratom to perform four year research that will enhance the operation and safety of the European nuclear power reactors. PASTELS (PAssive Systems: Simulating the Thermal-hydraulics with ExperimentaL Studies) deals with innovative passive safety systems and investigates the possibility of using reliable experimental data to assess the ability of various European thermal-hydraulic tools to simulate the behavior of these systems. GO-VIKING (Gathering expertise On Vibration ImpaKt In Nuclear power Generation), on the other hand, focuses on the hydraulic interaction between the coolant and crucial nuclear power plant components that are susceptible to flow-induced vibrations. Through experimental and numerical investigations, these interactions are further studied and improved modeling methodologies are developed. In the current paper, the global objectives of both projects, as well as the methodologies and the expected impacts are presented. Moreover, selected results are briefly discussed and conclusions are drawn
From robots to drones, the future of decommissioning operations – The CLEANDEM and XS-ABILITY projects
No full textIn recent years, there has been an increase in Dismantling & Decommissioning (D&D) operations of nuclear facilities, driven by the ageing of infrastructures and political decisions to phase out nuclear power. These operations, which can last from a few years to several decades, require mature and reliable techniques that meet international standards, local safety regulations, and radiation protection criteria. Despite developments in robotics, sensors, and digital tools that could reduce manual labor and risk exposure, their deployment remains limited due to financial and logistical constraints. The EU-funded projects CLEANDEM and XS-ABILITY address this challenge by upgrading advanced nuclear sensors and mounting most of them on autonomous terrestrial (CLEANDEM) and both terrestrial and aerial (XS-ABILITY) robots. These robots are and will be designed to assist operators by enabling continuous monitoring during D&D processes, reducing radiation exposure (CLEANDEM), and accessing hard-to-reach areas and difficult to measure radionuclides (XS-ABILITY). They also minimize human errors and organizational issues related to limited intervention time and repetitive tasks. CLEANDEM's results were showcased at its final workshop, and XS-ABILITY, launched October 1st 2024, will build upon these developments to further improve safety and efficiency in D&D operations. This work focuses on CLEANDEM's technical developments, and presents XS-ABILITY as one of its perspectives