Annals of Nuclear Energy最新文献

{"title":"Study on the mechanical behavior of penetrations in floating nuclear power plants under ocean swing load","authors":"Guan Guan ,&nbsp;Shiguang Du ,&nbsp;Boyu Huang ,&nbsp;Guopeng Liang ,&nbsp;Qu Yang","doi":"10.1016/j.anucene.2025.111224","DOIUrl":"10.1016/j.anucene.2025.111224","url":null,"abstract":"<div><div>For floating nuclear power plants (FNPP) operating at sea, the mechanical penetration assemblies (MPA) installed on FNPP are designed to withstand large wave-induced swing loads, so it puts forward higher requirements for the structural strength of MPA. Currently, the strength evaluation of MPA under swing load is still insufficient. A set of numerical simulation method for MPA is established, and the swing experiment is designed to verify the accuracy of the simulation results. The results show that the Mises stress of the MPA are far lower than the allowable stress of the material, and the structural strength is within the safe range; By comparing the relative error of the two data, the average error is 4.6 %, which is in line with the error threshold accepted in the engineering field. The effectiveness and accuracy of the numerical simulation method in predicting the behavior of MPA under swing loads are verified.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"214 ","pages":"Article 111224"},"PeriodicalIF":1.9,"publicationDate":"2025-01-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143159450","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Effect of bubble entrainment on thermal–hydraulic performance of LBE-cooled wire-wrapped rod bundles","authors":"Chunxi Wu ,&nbsp;Li Liu ,&nbsp;Haotian Luo ,&nbsp;Ruiqi Bao ,&nbsp;Junjie Yuan ,&nbsp;Maolong Liu ,&nbsp;Hanyang Gu","doi":"10.1016/j.anucene.2025.111218","DOIUrl":"10.1016/j.anucene.2025.111218","url":null,"abstract":"<div><div>The lead–bismuth fast reactor (LFR) is at risk of steam generator heat transfer tube rupture (SGTR), which could result in the entry of liquid lead–bismuth with bubble entrainment into the core, potentially impacting the thermal–hydraulic performance of the wire-wrapped rod bundles. In this study, a three-dimensional numerical model of the flow domain of 7-pin wire-wrapped rod bundles is established, in conjunction with the population balance model and the mixture two-phase flow model. Numerical simulation is conducted under cases of both liquid lead–bismuth single-phase flow and two-phase bubbly flow. The influence of inlet velocity, inlet void fraction, and inlet average bubble diameter on the thermal–hydraulic performance of wire-wrapped rod bundles is investigated. The study reveals that bubble entrainment leads to chaotic flow patterns and intensifies vortex phenomena. Bubbles tend to coalesce rather than rupture in the flow domain, and the average bubble diameter shows a positive correlation with the inlet void fraction. Furthermore, an increased inlet void fraction leads to higher rod wall temperature, overall Nusselt number, and friction factor. In contrast, an increase in the inlet average bubble diameter shows a negative correlation with the friction factor and overall Nusselt number.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"214 ","pages":"Article 111218"},"PeriodicalIF":1.9,"publicationDate":"2025-01-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143159443","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Generalized Levermore–Pomraning equations with memory effects","authors":"Alessandro Tentori ,&nbsp;Gérald Samba ,&nbsp;Andrea Zoia","doi":"10.1016/j.anucene.2025.111202","DOIUrl":"10.1016/j.anucene.2025.111202","url":null,"abstract":"<div><div>The Levermore–Pomraning (LP) equations allow obtaining approximate solutions to particle transport problems in Markov media, reducing the computation time compared to reference solutions resulting from sampling a collection of material realizations and solving for each of them the linear transport equation. The deterministic LP equations have a stochastic counterpart, the Chord Length Sampling (CLS) model, which can be easily implemented in a Monte Carlo particle-transport solver with minimal modifications. It is known that significant discrepancies may appear between exact and LP (or CLS) solutions, because of the memory-less nature of the LP (or CLS) model. Over the years, several CLS-like improved models have been proposed: greater accuracy with respect to reference solutions has been achieved by adding ‘spatial memory’ effects to the stochastic particle-transport algorithms. In this work, we present an enhanced-memory deterministic LP model in one-dimensional geometry, obtained by introducing a mathematical formalism to take into account memory effects in the LP equations. We will benchmark our results against the standard LP and CLS models, the improved CLS-like models, and the reference solutions for a set of spatially heterogeneous configurations.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"214 ","pages":"Article 111202"},"PeriodicalIF":1.9,"publicationDate":"2025-01-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143159451","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"A parametric statistical inference measure for input-based uncertainty quantification in BEPU analysis","authors":"Seyed Ali Hosseini ,&nbsp;Amir Saeed Shirani ,&nbsp;Reza Akbari ,&nbsp;Francesco D’Auria","doi":"10.1016/j.anucene.2025.111214","DOIUrl":"10.1016/j.anucene.2025.111214","url":null,"abstract":"<div><div>This work conducts a thorough input-based uncertainty quantification (IBUQ) and sensitivity analysis (SA) to assess the evolution of uncertainties during an SB-LOCA in a VVER-1000. First, the contributing uncertain parameters in the scenario are identified. Then, a framework coupling DAKOTA and RELAP5 is employed to preprocess input files, generated through Monte-Carlo sampling, and to post-process Figure-of-Merits (FOMs). As a novel contribution of this work, a parametric statistical measure, “Overlapping Index (OI)”, is conceptualized based on Gaussian-parametrized distributions, retrieved from different order statistics (OS). The cladding failure time (CFT), representing the exceedance of peak cladding temperature (PCT) beyond the threshold, is used to operationalize OI. Despite moderate skewness in the distributions, the results indicate that the OI can serve as a global confidence measure for IBUQ. Overall, OI enables a deeper understanding of uncertainties’ evolution, paving the path for probabilistic validation, and providing specific support for risk-informed decision-making.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"214 ","pages":"Article 111214"},"PeriodicalIF":1.9,"publicationDate":"2025-01-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143159453","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Feasibility study of Th–Pu based micro-heterogeneous duplex fuels in PT-SCWR","authors":"Shuvendu Shivam,&nbsp;Satya Sekhar Bhogilla,&nbsp;Goutam Dutta","doi":"10.1016/j.anucene.2025.111193","DOIUrl":"10.1016/j.anucene.2025.111193","url":null,"abstract":"<div><div>The shortage of uranium and the growing demand for clean and reliable energy make it urgent need to explore alternative fuels. The development and implementation of thorium-based fuel can help in solving key challenges faced by the nuclear industry. This study addresses the challenges of limited natural uranium supply, nuclear waste management and proliferation concerns by exploring the use of duplex fuel in the PT-SCWR. The PT-SCWR Generation IV reactor types represents next stage of advancement in the nuclear reactor field with enhanced efficiency. Micro-heterogeneous duplex fuel may help in extending the burnup cycle and provide various operational benefits. This feasibility study explores the potential use of duplex fuel in PT-SCWR by analyzing its neutron-physical properties at both the pin-cell and 64-element fuel assembly levels. A series of 2-D lattice physics calculations with depletion is conducted using the DRAGON code with particular emphasis on burnup depth, reactivity coefficients, and fissile inventory. The computational model is verified against the PWR AP1000 pin cell model which demonstrated trends consistent with existing literature. The results are categorized into two different categories named performance metrics and operational safety characteristics. Homogeneous fuel served as a baseline for comparison, while different enrichment levels of fissile concentration (<span><math><mrow><mn>5</mn><mtext>%</mtext><mo>≤</mo><mtext>%</mtext><msub><mrow><mi>PuO</mi></mrow><mrow><mn>2</mn></mrow></msub><mo>≤</mo><mn>20</mn><mtext>%</mtext></mrow></math></span>) were analyzed in duplex configuration. It is observed in performance evaluations that duplex pellets exhibit smoother infinite multiplication factor curves which leads to increased cycle burnups and lower initial reactivity with a slower rate of reactivity decline. Safety evaluations revealed negative temperature coefficients of reactivity and supports nuclear non-proliferation due to its lower fissile inventory ratio (FIR). The micro-heterogeneous duplex pellet emerges as a viable fuel option for PT-SCWR fuel providing several performance and safety benefits to its predecessor.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"214 ","pages":"Article 111193"},"PeriodicalIF":1.9,"publicationDate":"2025-01-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143160474","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Design space analysis for a NaCl-UCl3 based breed and burn reactor system","authors":"Yu Peng ,&nbsp;Guifeng Zhu ,&nbsp;Hongyan Wang ,&nbsp;Ailin Yao ,&nbsp;Ying Song ,&nbsp;Miaomiao Niu","doi":"10.1016/j.anucene.2025.111225","DOIUrl":"10.1016/j.anucene.2025.111225","url":null,"abstract":"<div><div>The design space for a molten chloride salt fast reactor utilizing the NaCl-UCl₃ salt in breeding and burning mode was investigated employing a neutron balance method for mixed liquid fuels with varying molar UCl₃ concentrations. An infinite one-cell core was adopted as the physical model to calculate static neutrons based on critical search methodology and to perform burn-up calculations concerning the evolution of neutron balance. The results indicate that the NaCl-UCl₃ system demonstrates favorable breeding characteristics and possesses exceptional inherent core safety. Furthermore, the minimum burnup requirement is intricately associated with UCl₃ molar concentrations; an increase in molar content results in a more rapid attainment of the neutron balance state and a reduction in the minimum burnup requirement. Additionally, considering the neutron loss term, an increase in UCl₃ molar contents from 0.30 to 0.50 correlates with an enhancement in the maximum tolerable neutron loss term, rising from 6.263% to 13.145%.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"214 ","pages":"Article 111225"},"PeriodicalIF":1.9,"publicationDate":"2025-01-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143160473","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"On LVR-15 radioisotope production capabilities","authors":"Peter Krásny,&nbsp;Branislav Belko","doi":"10.1016/j.anucene.2025.111184","DOIUrl":"10.1016/j.anucene.2025.111184","url":null,"abstract":"<div><div>The LVR-15 research reactor is operated as a multi-purpose reactor with the utilization tending more towards material research in the reactor’s early years. Later after optimizing of the operation and active core loads, the reactor became also a stable and reliable part in the supply chain of medical radioisotopes, especially ⁹⁹Mo. Nowadays, the radioisotopes production is a well established activity of the LVR-15 facility. Many different types of radioisotopes have been produced. With the increased demand for radioisotopes, especially for nuclear medicine and limited availability of the current reactor fleet, a study was performed to increase the possible production capabilities of the LVR-15. The present production possibilities are discussed in the following paper with their possible expansion involving an irradiation channel mounted in the E7 reactor position. The study is performed using experimentally validated calculation models and methods comprising neutron spectra calculation using the MCNP code and further activity determination by the FISPACT-II code. Reasonably achievable activities of the products are determined. Additionally, the self-shielding effect of the target material size was also evaluated.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"214 ","pages":"Article 111184"},"PeriodicalIF":1.9,"publicationDate":"2025-01-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143159452","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"Reprocessed fuels in a PWR SMR based on NuScale","authors":"Samuel Fernandes ,&nbsp;Lucas Chaves ,&nbsp;João P. Cunha Melo ,&nbsp;Karytha M.S. Corrêa ,&nbsp;Natália Gonçalves ,&nbsp;Teresa Barrachina ,&nbsp;Rafael Miró ,&nbsp;Claubia Pereira","doi":"10.1016/j.anucene.2024.111148","DOIUrl":"10.1016/j.anucene.2024.111148","url":null,"abstract":"<div><div>This work evaluated reprocessed fuels in a core model based on a NuScale, a PWR Small Modular Reactor (SMR). With a model starting from the equilibrium core, this work suggests the replacement of fresh UO₂ fuel with reprocessed fuels. It evaluated two types of reprocessed fuels: spiked with thorium and spiked with depleted U (0.2%). The main aim is to analyze the core burnup process with reprocessed fuels inserted in some assemblies and analyze the depleted spent fuel composition, multiplication factor during burnup, power distribution, leakage, and core activity. The core was modeled and simulated using the MC code SERPENT 2.2.1. As expected, the activity values for the models with reprocessed fuels are higher. The model with thorium has the highest activity and leakage. The k_eff s during burnup are higher for reprocessed fuels, which could lead to an extension of the burnup. The change in power distribution is minimal. It is necessary to advance the evaluation of reprocessed fuels to ensure a better destination for radioactive waste, as well as a better destination for depleted uranium. This material has shown promising results in reprocessed fuel analysis.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"214 ","pages":"Article 111148"},"PeriodicalIF":1.9,"publicationDate":"2025-01-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143160472","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"The key PSF in intelligent nuclear power plant main control room: From the perspective of trust and reliance","authors":"Yuhao Xie ,&nbsp;Beiyuan Guo ,&nbsp;Ming Jia ,&nbsp;Zhihui Xu ,&nbsp;Xiliang Tao","doi":"10.1016/j.anucene.2025.111192","DOIUrl":"10.1016/j.anucene.2025.111192","url":null,"abstract":"<div><div>HRA represents the latest understanding of human performance in the socio-technical system and should be integrated iteratively with the system implementation process. Some Fields have already initiated intelligent transformation, and the nuclear power field also will be entering that. However, fully unmanned systems are still impossible, human reliability will continue to be crucial in intelligent systems. PSFs play a significant role in HRA, including risk prevention, risk quantification and risk traceability. Given this consideration, this study conducted a predictive exploration of PSFs for intelligent NPP MCR. We emphasized the necessity of incorporating trust and reliance into the HRA process and identified factors that affect them based on an impact framework, considering these factors as key PSFs. The findings of this study can inform risk prevention strategies for intelligent NPP MCR and provide guidance for risk traceability efforts.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"214 ","pages":"Article 111192"},"PeriodicalIF":1.9,"publicationDate":"2025-01-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143160470","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"A half-century of nuclear research, education and training: Story of the JSI TRIGA reactor","authors":"Luka Snoj ,&nbsp;Klemen Ambrožič ,&nbsp;Loïc Barbot ,&nbsp;Ljudmila Benedik ,&nbsp;Arne Bratkič ,&nbsp;Ivana Capan ,&nbsp;Christelle Reynard-Carette ,&nbsp;Vladimir Cindro ,&nbsp;Dušan Čalič ,&nbsp;Christophe Destouches ,&nbsp;Benoit Geslot ,&nbsp;Alireza Haghighat ,&nbsp;Romain Henry ,&nbsp;Milena Horvat ,&nbsp;Elchin M. Huseynov ,&nbsp;Grégoire de Izarra ,&nbsp;Radojko Jaćimović ,&nbsp;Anže Jazbec ,&nbsp;Igor Jenčič ,&nbsp;Robert Jeraj ,&nbsp;Tanja Goričanec","doi":"10.1016/j.anucene.2024.111122","DOIUrl":"10.1016/j.anucene.2024.111122","url":null,"abstract":"<div><div>The TRIGA Mark II research reactor at the Jožef Stefan Institute is a key facility in the field of nuclear research, characterized by its versatility and applicability in a wide range of scientific disciplines. This document highlights its operational history, contributions to nuclear safety, education and various scientific applications, including advances in reactor and radiation physics, neutron activation analysis, environmental science and even contributions to the fight against the COVID-19 pandemic. It highlights the reactor’s significant role in fostering international collaborations, improving computer modeling techniques for nuclear research, and providing invaluable educational experiences. The great versatility and applicability of the JSI TRIGA reactor is emphasized by its adaptability to various research needs and its ability to enable groundbreaking studies in both fundamental and applied sciences.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"214 ","pages":"Article 111122"},"PeriodicalIF":1.9,"publicationDate":"2025-01-21","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143160374","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"OA","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}