Annals of Nuclear Energy最新文献

{"title":"Effect of swirling strength on droplets impact on concave wall: Experimental and numerical investigation","authors":"Shuo OUYANG ,&nbsp;Zhenqin Xiong ,&nbsp;Hua Bei ,&nbsp;Kaicheng Yu ,&nbsp;Lichen Xue ,&nbsp;Jiyun Zhao","doi":"10.1016/j.anucene.2025.111282","DOIUrl":"10.1016/j.anucene.2025.111282","url":null,"abstract":"<div><div>Droplets impact on walls in a rotating gas–liquid flow field is common in industrial applications. To reveal the effect of swirling strength on droplet impact outcome, droplet trajectory and impingements on the concave wall with three kinds of swirlers are investigated by numerical simulation and experiment. Three impact outcomes are observed: downward slide spreading, horizontal slide spreading, and upward slide spreading. It is found that the swirling strength affects the impact outcome and the spreading factors. The transition from the upward slide spreading to other impact outcomes is promoted by increasing the swirling strength. Moreover, a theoretical model is deduced for the maximum transverse spreading factor of the droplets impact on the concave wall in a rotating gas flow field by modifying the surface energy and adding the auxiliary dissipation. The discrepancies between the predicted maximum transverse spreading factors and the experimental results are in the range of + 5 %∼-10 %.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111282"},"PeriodicalIF":1.9,"publicationDate":"2025-03-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685348","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":"Preliminary criticality analysis of a partially damaged reactor core under different scenarios","authors":"Hoang Hai Nguyen","doi":"10.1016/j.anucene.2025.111361","DOIUrl":"10.1016/j.anucene.2025.111361","url":null,"abstract":"<div><div>This study examined the criticality characteristics of a partially damaged reactor model, in which fuels located at the core center melt into fuel debris of varying shapes, while fuels situated at the core edge remain intact. The investigation was conducted using the Serpent code with the JENDL-5 library. The results indicate that when the volume of fuel debris is constant, the shape of the fuel debris does not cause significant alterations in the variation of the k_eff of the system. In contrast, for the scenario of the variable fuel-debris volume, the k_eff variation law can be divided into two groups for the reference case with a system temperature of 300 K and no boron in the water. The first group comprises fuel debris with cuboid and cylindrical shapes, while the second group includes spherical, conical, and truncated conical shapes.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111361"},"PeriodicalIF":1.9,"publicationDate":"2025-03-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685356","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":"Study on effect of impact parameter on droplets successively impacting on liquid film by CLSVOF method","authors":"Bowen Chen ,&nbsp;Yandong Hou ,&nbsp;Chuntian Gao ,&nbsp;Weichao Li ,&nbsp;Yuyang Wang ,&nbsp;Ruifeng Tian","doi":"10.1016/j.anucene.2025.111359","DOIUrl":"10.1016/j.anucene.2025.111359","url":null,"abstract":"<div><div>In the corrugated plate dryer, there are a lot of phenomena of multi-droplets impacting on the liquid film. Therefore, the analysis of droplets successively impacting on liquid film has important engineering significance. In this paper, the CLSVOF method is used to simulate the successive impact of two droplets on the liquid film. By analyzing the velocity and pressure distribution of the liquid film and the motion state of the residual film, the influence of the droplets spacing, the initial liquid film thickness and the impact velocity on the impact outcomes is obtained, and the influence mechanism is analyzed. The simulation results show that the inner crown is easy to splash with the increase of the droplets spacing; with the increase of impact velocity, the inner crown is easy to splash；with the increase of the initial liquid film thickness, the inner crown is not easy to splash.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111359"},"PeriodicalIF":1.9,"publicationDate":"2025-03-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685358","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 hybrid optimized Picard method for neutronic/thermal-hydraulic coupling problem","authors":"Xinru Peng,&nbsp;Han Zhang,&nbsp;Lixun Liu,&nbsp;Qinrong Dou,&nbsp;Yingjie Wu,&nbsp;Jiong Guo,&nbsp;Fu Li","doi":"10.1016/j.anucene.2025.111380","DOIUrl":"10.1016/j.anucene.2025.111380","url":null,"abstract":"<div><div>Picard iteration is a widely-used method for Neutronic/Thermal-Hydraulic (N/TH) coupling calculation in nuclear reactor, but it usually suffers from computational efficiency and stability, especially for complicated large-scale coupling issues. Residual balance method (RB) and Anderson acceleration method (AA) are two well-known optimized variants, where the former focusing on reducing the computational cost per outer iteration by adaptive tolerance, and the latter on decreasing the number of outer nonlinear iterations by using multiple iteration history information. However, combining these two methods causes incompatibility because the inaccurate function evaluations from the adaptive tolerance in the inner iterations disrupt the convergence rate of Anderson acceleration. In this work, a new hybrid optimized Picard iteration method (Picard-H) is proposed to combine the advantages of residual balance method and Anderson acceleration method by using an adaptive switching factor, avoiding the incompatibility from the inner iteration when approaching convergence. This new method could further enhance the efficiency of Anderson Acceleration, which could finish calculation much faster than both RB and Picard. A simplified neutronic k-eigenvalue problem in PWR with thermal–hydraulic feedback effect is utilized to evaluate the performance of the new optimized Picard method. The results demonstrate that for the simplified PWR model, the Picard-H method is 10% more computationally efficient than the AA method, more than twice as fast as the RB method, and more than four times faster than the traditional Picard method. In addition, the simple combination of RB and AA methods diverges due to the inexact fixed-point mapping function evaluation from the RB method. Furthermore, the hybrid method is robust against variations in parameters, such as the bounding parameter in the residual balance method and the memory depth in Anderson acceleration. The computational performance of the new method also is not sensitive to the choice of switching factor which is suggested to be adaptive when the residual drops to about 2 to 3 orders of magnitude of the initial residuals. The supplementary numerical results from the simplified HTR-10 model confirm that the Picard-H method exhibits 5% greater computational efficiency than the AA method and is over nine times faster than the traditional Picard method and the RB method.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111380"},"PeriodicalIF":1.9,"publicationDate":"2025-03-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685357","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 validation of neutron transport in chlorine in LR-0 reference field","authors":"Tomáš Peltan ,&nbsp;Tomáš Czakoj ,&nbsp;Vlastimil Juříček ,&nbsp;Evžen Losa ,&nbsp;Jan Šimon ,&nbsp;Michal Košťál","doi":"10.1016/j.anucene.2025.111356","DOIUrl":"10.1016/j.anucene.2025.111356","url":null,"abstract":"<div><div>Nuclear energy is one of the promising ways of reaching carbon neutrality, but this goal requires the development of new reactor types. One such concept is the molten salt reactor system, which uses chlorine-based fuel salts. Developing this system needs reliable neutronic data for all materials used, with particular emphasis on core components. While uranium cross-sections remain well-studied, sufficient experimental data for chlorine is lacking, particularly for validations of current data evaluations. This paper presents new, precise integral experiments to validate various chlorine cross-section evaluations. Notably, compared with experimental results, the currently available data sets exhibit significant discrepancies, suggesting that simulations based on current nuclear data evaluations may be unreliable.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111356"},"PeriodicalIF":1.9,"publicationDate":"2025-03-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685350","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":"Seaknot: Looking ahead of severe accident research","authors":"L.E. Herranz ,&nbsp;S. Gupta ,&nbsp;S. Paci ,&nbsp;P. Piluso","doi":"10.1016/j.anucene.2025.111390","DOIUrl":"10.1016/j.anucene.2025.111390","url":null,"abstract":"<div><div>Severe Accidents (SAs) dominate the risk associated to the commercial production of nuclear energy. Despite the major achievements made in their research, still existing gaps, upcoming new technologies as Accident Tolerant Fuels (ATFs) and Small Modular Reactors (SMRs), more stringent safety requirements, optimization of SA management, and other factors, point the need for an efficient use of research resources in the years to come. Three major elements should integrate any SA roadmap to be proposed: preservation of knowledge and know-how; identification of key issues which research would result in the best accident management (AM) feasible; and, no less important, strengthening the workforce who will be responsible for such research. The SEAKNOT project (SEvere Accident research and KNOwledge managemenT for LWRs) was born to address this need in all and every aspect. The present article outlines the major pillars of SEAKNOT and synthesizes the progress made since its onset at the end of 2022. The methodologies adopted to develop a SA PIRT (Phenomena Identification and Ranking Table) and to build a Validation Database Directory (VADD) are described along with the ongoing phenomena listing and ranking. Besides, the first steps towards an experimental infrastructure capable of dealing with present and future needs (SAINET) are included. No less relevant the actions already made and the novelties coming on the side of knowledge and know-how transfer are also discussed.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111390"},"PeriodicalIF":1.9,"publicationDate":"2025-03-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685349","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":"Local angular adaptivity CADIS hybrid variance reduction method for monte carlo radiation transport calculations","authors":"Yufan Zhao ,&nbsp;Jingru Han ,&nbsp;Jiaxu Zuo ,&nbsp;Jiaju Hu ,&nbsp;Fudong Liu ,&nbsp;Bin Zhang","doi":"10.1016/j.anucene.2025.111385","DOIUrl":"10.1016/j.anucene.2025.111385","url":null,"abstract":"<div><div>The Consistent Adjoint Driven Importance Sampling (CADIS) method is a highly effective Monte Carlo (MC) hybrid variance reduction technique; however, its acceleration effects are significantly limited in strongly angular dependent shielding problems involving complex channels. Based on the theory of angular adaptivity, a local angular adaptivity CADIS (LAA-CADIS) hybrid acceleration method is proposed. This method enhances the accuracy of the quadrature set by dynamically adjusting the discrete angular distribution in important regions, thereby better capturing the anisotropic characteristics of angular flux density. The IRI-TUB straight channel benchmark model is selected to validate the acceleration effects of LAA-CADIS. Numerical results indicate that, under the same error conditions, the computational efficiency of LAA-CADIS improves by 34% compared to CADIS. LAA-CADIS accurately describes the neutron importance distribution in strongly angular-dependent shielding models, significantly enhancing Monte Carlo calculation efficiency.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111385"},"PeriodicalIF":1.9,"publicationDate":"2025-03-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685354","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":"Adapting a machine learning method for the source discrimination of plutonium samples mixed from multiple reactor types","authors":"Patrick J. O’Neal,&nbsp;Sunil S. Chirayath","doi":"10.1016/j.anucene.2025.111271","DOIUrl":"10.1016/j.anucene.2025.111271","url":null,"abstract":"<div><div>Plutonium (Pu) samples that are sourced from multiple, different reactor types present a challenge to nuclear forensics investigations. Previous studies have developed a nuclear forensics methodology capable of identifying a Pu sample’s reactor type of origin using isotope ratios as features in machine learning classification models. However, the models could only attribute Pu sourced from a single reactor type. The methodology was adapted to discriminate between Pu produced from the six original single reactor type classes and twelve new classes comprised of binary mixtures of the six original reactor type classes. This adaptation was a success, with a support vector machine (SVM) identified as the most suitable model type for the task. The model’s sensitivity to different groups of features was examined and the model was also validated with data from experimentally produced Pu samples, in both single reactor type and mixed reactor type cases.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111271"},"PeriodicalIF":1.9,"publicationDate":"2025-03-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685351","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":"GeN-Foam and OpenMC simulation for multi-physics analysis of fast-spectrum molten salt reactor with beryllium oxide reflector","authors":"Wooseong Park,&nbsp;Yong Hoon Jeong","doi":"10.1016/j.anucene.2025.111378","DOIUrl":"10.1016/j.anucene.2025.111378","url":null,"abstract":"<div><div>Recent interest in fast-spectrum molten salt reactors (F-MSRs) has promoted the need for multi-physics analysis. Specifically, the cavity core configuration requires an analysis on unstructured domain, promoting the development of OpenFOAM-based multi-physics codes. Concurrently, beryllium oxide (BeO) has been suggested as a promising reflector material for F-MSRs due to its favorable neutronics performance. However, the use of BeO introduces a highly skewed power distribution towards the wall, potentially leading to significant hot spot zones and distinctive neutronics fields. Accordingly, this study conducted multi-dimensional, multi-physics analysis of a F-MSR core with BeO reflector. GeN-Foam served as the primary multi-physics analysis tool using multi-group diffusion approach with group constants provided by OpenMC. Firstly, this study validated the applicability of GeN-Foam to BeO applications and the accuracy of group constants through pure neutronics simulation. Subsequenlty, multi-physics analysis was performed on MSFR-like geometry, revealing the distinctive characteristics of BeO reflector in F-MSRs.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111378"},"PeriodicalIF":1.9,"publicationDate":"2025-03-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685352","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":"Neutron transmission measurement of thick natFe targets at nELBE","authors":"A.R. Junghans ,&nbsp;R. Beyer ,&nbsp;R. Capote ,&nbsp;D. Bemmerer ,&nbsp;T. Hensel ,&nbsp;T. Kögler ,&nbsp;S.E. Müller ,&nbsp;K. Römer ,&nbsp;K. Schmidt ,&nbsp;R. Schwengner ,&nbsp;S. Turkat ,&nbsp;J. Turko ,&nbsp;S. Urlaß","doi":"10.1016/j.anucene.2025.111363","DOIUrl":"10.1016/j.anucene.2025.111363","url":null,"abstract":"<div><div>High-resolution neutron transmission measurements of natural iron have been performed in the fast neutron range from 100<!--> <!-->keV to 12<!--> <!-->MeV using the nELBE time-of-flight experiment at the Helmholtz-Zentrum Dresden-Rossendorf (HZDR) with a flight path of 868.34(30) cm. The measurements were carried out using three different iron samples of 20, 50 and 90mm thickness. The neutron transmission and effective total cross section were determined as a function of neutron energy, and the results were compared with existing evaluations and previous measurements. The measurements revealed significant shortcomings in the resolved resonance region of current evaluations, particularly in the energy range from 100 to 700 keV. The results of this work have already been used to improve the INDEN evaluation for the Fe-isotopes, which have been adopted by the ENDF/B-VIII.1 library and proposed for JEFF-4. The high-resolution time-of-flight measurements provide valuable new data for the development of more accurate nuclear data evaluations for natural iron.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"218 ","pages":"Article 111363"},"PeriodicalIF":1.9,"publicationDate":"2025-03-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143685353","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}