Annals of Nuclear Energy最新文献

{"title":"Adjusting JEFF-3.3 actinide data using a new, dedicated methodology for selecting suited assimilation database parameters","authors":"Sandro Pelloni, Dimitri Rochman","doi":"10.1016/j.anucene.2025.111246","DOIUrl":"10.1016/j.anucene.2025.111246","url":null,"abstract":"<div><div>A general method is proposed to choose, among several benchmarks, suitable assimilation database parameters to be used in adjustments. All these benchmarks are predetermined keeping in mind specific goals of the data assimilation. The main principle of the novel methodology is that of excluding groups of strongly cross-correlated computed parameters by estimating their posterior values of <span><math><mrow><msup><mrow><mi>χ</mi></mrow><mn>2</mn></msup></mrow></math></span>. The assimilation tries minimizing the mean <span><math><mrow><msup><mrow><mi>χ</mi></mrow><mn>2</mn></msup></mrow></math></span> for the entirety of the considered benchmarks, including those target parameters which are not part of the selected assimilation database.</div><div>The methodology currently applied to the JEFF-3.3 library, is demonstrated by adjusting data for <sup>235</sup>U, <sup>238</sup>U, <sup>239</sup>Pu and <sup>240</sup>Pu in conjunction with a class of integral parameters (effective multiplication factors) of fast criticalities including the Godiva and Jezebel spheres, for which the effect of varying resonance parameters in the calculations may be largely neglected.</div><div>The computed mean <span><math><mrow><msup><mrow><mi>χ</mi></mrow><mn>2</mn></msup></mrow></math></span> of 36 values in total, among which seven refer to the assimilation database, is halved, and the variance of the individual <span><math><mrow><msup><mrow><mi>χ</mi></mrow><mn>2</mn></msup></mrow></math></span>-values decreases by a factor of 6 with respect to the prior values. More explicitly, the posterior values of respectively 1.10 and 3.77 for <span><math><mrow><msup><mrow><mi>χ</mi></mrow><mn>2</mn></msup></mrow></math></span> and the variance of the individual <span><math><mrow><msup><mrow><mi>χ</mi></mrow><mn>2</mn></msup></mrow></math></span>-values are much smaller than the corresponding prior values of 2.32 and 22.38, which is significant.</div><div>As regards the adjustment, for <sup>235</sup>U, it is found that <span><math><mrow><mover><mrow><mi>μ</mi></mrow><mrow><mo>¯</mo></mrow></mover></mrow></math></span> and the inelastic scattering cross-section respectively decrease by maximum 3% and 2.6%; <span><math><mrow><mover><mrow><mi>ν</mi></mrow><mrow><mo>¯</mo></mrow></mover></mrow></math></span> is uniformly decreased by maximum 0.053% and the fission spectrum is somewhat harder. For <sup>238</sup>U, <span><math><mrow><mover><mrow><mi>μ</mi></mrow><mrow><mo>¯</mo></mrow></mover></mrow></math></span> increases by maximum 5.4% and the inelastic scattering cross-section is lowered by 1%. For <sup>239</sup>Pu, <span><math><mrow><mover><mrow><mi>ν</mi></mrow><mrow><mo>¯</mo></mrow></mover></mrow></math></span> is uniformly increased by maximum 0.027% and the fission spectrum is slightly softer. For <sup>240</sup>Pu, the fission cross-section is decreased by maximum 3.9%. The proposed adjustments are well within the uncertainty limit of one standard deviation for the","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"215 ","pages":"Article 111246"},"PeriodicalIF":1.9,"publicationDate":"2025-02-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143348271","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 modified A* algorithm for path planning in the radioactive environment of nuclear facilities","authors":"Biao Zhang ,&nbsp;Xingfu Cai ,&nbsp;Guoqiang Li ,&nbsp;Xiaomeng Li ,&nbsp;Minjun Peng ,&nbsp;Miao Yang","doi":"10.1016/j.anucene.2025.111233","DOIUrl":"10.1016/j.anucene.2025.111233","url":null,"abstract":"<div><div>The search efficiency is low when using the traditional A* algorithm for radiation field path planning. In order to prevent the situation where one of the two cost functions of <em>F</em>(<em>n</em>) in the A* algorithm is significantly larger than the other, this paper presents a predicted cost method as a heuristic function of the A* algorithm and creates a weighting scheme to balance the actual and predicted costs in the A* algorithm. The results of path planning show that the modified A* algorithm has a search direction, which increases algorithm efficiency while guaranteeing low dose. The total cumulative dose of the route of the modified A* algorithm is better than that of the traditional A* algorithm and probabilistic road map method(PRM). The calculation results of the two models show that the modified A* algorithm is slightly lower than the traditional A* algorithm in terms of cumulative dose, which is reduced by 5.35% compared with the PRM algorithm. In terms of the number of algorithm execution points, the modified A* algorithm is 57.18% lower than the traditional A* algorithm on average. In terms of calculation time, the modified A* algorithm is 13.79% shorter than the traditional A* algorithm. The PRM algorithm has the shortest time, but the results of the PRM algorithm are random and unstable. The modified A* algorithm has the search direction under the premise of keeping the low dose, which improves the efficiency of the algorithm. Therefore, the modified A* algorithm can be used as an effective reference for staff path planning.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"214 ","pages":"Article 111233"},"PeriodicalIF":1.9,"publicationDate":"2025-02-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143224605","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 novel methodology to scientifically justify the formulation of modeling assumptions in screening analysis of Probabilistic Risk Assessment (PRA)","authors":"Sari Alkhatib,&nbsp;Tatsuya Sakurahara,&nbsp;Seyed Reihani,&nbsp;Zahra Mohaghegh","doi":"10.1016/j.anucene.2025.111237","DOIUrl":"10.1016/j.anucene.2025.111237","url":null,"abstract":"<div><div>In Probabilistic Risk Assessment (PRA) of nuclear power plants (NPPs), there is a growing reliance on modeling and simulation ( M&amp;S). Due to time and resource constraints, PRA analysts do not conduct M&amp;S for every PRA event or its underlying factors; instead, they selectively, through screening analysis, determine the required level of realism for M&amp;S. Since plant data for estimating the values of input parameters may not yet be fully collected, modeling assumptions would be required. This paper proposes a new approach for systematically selecting a set of proper modeling assumptions that minimize a false negative result in the screening analysis. The proposed methodology conducts uncertainty quantification and sensitivity analysis and generates a sensitivity dataset, which can then be utilized to guide and justify modeling assumptions to generate surrogate values of M&amp;S input parameters. The proposed methodology is applied to the screening analysis of a multi-compartment fire scenario at an NPP.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"214 ","pages":"Article 111237"},"PeriodicalIF":1.9,"publicationDate":"2025-02-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143224606","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":"Uncovering the potential of ZnO and CaO in shielding and density enhancement for borate glass systems","authors":"M.I. Sayyed ,&nbsp;Laith Ahmed Najam ,&nbsp;K.A. Mahmoud ,&nbsp;Berivan F. Namaq ,&nbsp;Taha Yaseen Wais ,&nbsp;Yasser Maghrbi","doi":"10.1016/j.anucene.2025.111231","DOIUrl":"10.1016/j.anucene.2025.111231","url":null,"abstract":"<div><div>In the current work, the physical and radiation shielding properties for a glass system composed of (65-x-y) B₂O₃ + 10BaO + 10Na₂O+(10 + x) ZnO+(5 + y) CaO; x = y = 0, 5, 10, and 15 mol% were examined experimentally. The density of the prepared glass samples was examined using the Archimedes method, where the density of prepared samples increased between 3.126 ± 0.066 g/cm³ and 3.731 ± 0.076 g/cm³ when the B₂O₃ compound was partially substituted by ZnO and CaO compounds. Additionally, the narrow beam transmission method and a 2″ × 2″ NaI (Tl) scintillation detector were utilized to measure the γ-ray shielding ability of prepared glass samples over an energy range of 0.662–1.332 MeV emitted by the radioactive sources Cs-137 and Co-60. The experimental measurements were also validated using the Monte Carlo simulation method. The difference between the two approaches is ±5 %. The measurements depict an enhancement in the linear attenuation coefficient with increasing the B₂O₃ substitution by ZnO and Ca compounds. The linear attenuation coefficient increases by 17.83 %, 18.30 %, 18.22 %, and 18.14 % at 0.662 MeV, 1.173 MeV, 1.252 MeV, and 1.332 MeV, respectively, as ZnO + CaO rise across the concentration of 15 mol%–45 mol%.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"214 ","pages":"Article 111231"},"PeriodicalIF":1.9,"publicationDate":"2025-02-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143224904","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":"Spectral analysis of time-dependent impact force in high-speed liquid droplet impact","authors":"Kei Fujisawa","doi":"10.1016/j.anucene.2025.111216","DOIUrl":"10.1016/j.anucene.2025.111216","url":null,"abstract":"<div><div>High-speed liquid droplet impacts are a fundamental problem in various engineering applications. This study addresses the decomposition of the time-dependent impact force during high-speed [<em>O</em> (100 m/s)] liquid droplet impingement (LDI). The force was decomposed into low (transient force) and high-frequency components (oscillatory force) via dynamic mode decomposition (DMD), and the effect of varying the impact Mach number on the spectral characteristics of the time-dependent impact force was examined. The frequency of the oscillatory force during high-speed LDI was analyzed for various impact Mach numbers, and a simple model was presented. The results provide valuable insight into the time-dependent impact force during high-speed LDI.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"214 ","pages":"Article 111216"},"PeriodicalIF":1.9,"publicationDate":"2025-02-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143224607","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":"Evaluation of different external neutron sources for a hybrid system based on the SEALER reactor","authors":"João P.C. Melo ,&nbsp;Lucas V.G. Chaves ,&nbsp;Samuel V.F. Silva ,&nbsp;Jefferson Duarte ,&nbsp;Karytha M.S. Corrêa ,&nbsp;Natália G.P.L. Oliveira ,&nbsp;José Cassimiro ,&nbsp;Carlos E. Velasquez ,&nbsp;Clarysson A.M. da Silva ,&nbsp;Claubia Pereira","doi":"10.1016/j.anucene.2025.111234","DOIUrl":"10.1016/j.anucene.2025.111234","url":null,"abstract":"<div><div>This work analyzed a hybrid modular system based on the SEALER. The original SEALER core has been modified to design the subcritical system for actinides transmutation. In this modification, the central fuel assembly was replaced with a lead target and an external neutron source, a crucial component that facilitates the transmutation process, and the UO₂ fuel, originally enriched to 19.75 %, has been substituted with reprocessed spent fuel. Two external neutron sources have been evaluated: a fusion neutron source based on an isotropic source with a deuterium–tritium (²H–³H) neutron spectrum calculated according to the plasma specifications of the Affordable Robust Compact (ARC) type tokamak reactor and a neutron source produced from spallation reactions with a natural lead target. The main goal was to evaluate the possibility of the hybrid system transmuting different reprocessed fuels: oxide-based spiked with thorium and depleted U ((TRU,Th)O₂ and (TRU,DU)O₂) and also nitrites spiked with the same elements ((TRU,Th)N e (TRU,DU)N). The results showed its possible viability.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"214 ","pages":"Article 111234"},"PeriodicalIF":1.9,"publicationDate":"2025-02-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143224905","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":"Collapsed energy group structure for analysis of prismatic high-temperature gas-cooled reactor with uranium fuel","authors":"Satoshi Takeda ,&nbsp;Takanori Kitada ,&nbsp;Akio Yamamoto ,&nbsp;Kazuya Yamaji ,&nbsp;Hiroki Koike ,&nbsp;Koji Asano","doi":"10.1016/j.anucene.2025.111238","DOIUrl":"10.1016/j.anucene.2025.111238","url":null,"abstract":"<div><div>Considering computational costs, it is practical to use collapsed energy group structures with less than several tens of groups of the core analysis of High-Temperature Gas-cooled Reactors (HTGRs). This study evaluates the performance of several existing energy group structures and newly optimized 15-group and 25-group structures for prismatic HTGRs with uranium fuel. Both multi-element and two-dimensional core geometries were used to account for neutron spectrum interference effects caused by the presence of control rods, differences in graphite temperature, and variations in the amount of surrounding graphite. The optimization calculations were performed using Genetic algorithm and Particle swarm optimization. Among the group structures with around 15 groups, the newly optimized 15-group structure showed relatively good agreement with the reference solution. For the group structures with around 25 groups, while the newly optimized 25-group structure showed slightly better performance under certain conditions, the existing 26-group structure consistently demonstrated stable and good performance.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"214 ","pages":"Article 111238"},"PeriodicalIF":1.9,"publicationDate":"2025-02-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143160478","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":"Development of transport solver based on Hybrid Finite Element Method in Griffin","authors":"Yeon Sang Jung ,&nbsp;Yaqi Wang ,&nbsp;Changho Lee","doi":"10.1016/j.anucene.2024.111128","DOIUrl":"10.1016/j.anucene.2024.111128","url":null,"abstract":"<div><div>A new lower-order transport solver option based on the Hybrid Finite Element Methods (HFEM) was implemented in Griffin, the MOOSE-based reactor physics code, to support core design calculations for advanced reactor applications. The HFEM formulation with spherical harmonics expansion (PN), also known as the variational nodal method, effectively solves spatially homogenized problems with strong transport effects. The residual evaluations of the HFEM weak form were derived and implemented in Griffin, with PN and diffusion options available in the new HFEM-based transport solver. The red-black iteration and the Coarse Mesh Finite Difference (CMFD) acceleration schemes are incorporated within the Richardson iteration framework to effectively solve the HFEM formulation. Performance tests conducted using the simplified ABTR benchmark problems demonstrated that the HFEM-based transport solver is a preferable option for solving problems with spatial homogenization and significant streaming effects, providing superior accuracy with appropriate p-refinement.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"214 ","pages":"Article 111128"},"PeriodicalIF":1.9,"publicationDate":"2025-02-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143160475","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 composite fault diagnosis method for nuclear power plant rotor system based on symmetrized dot pattern and residual neural network","authors":"Wenzhe Yin,&nbsp;Hong Xia,&nbsp;Xueying Huang,&nbsp;Wenhao Ran,&nbsp;Chunjie Zhao","doi":"10.1016/j.anucene.2024.111029","DOIUrl":"10.1016/j.anucene.2024.111029","url":null,"abstract":"<div><div>Composite faults caused by coupling different types of faults increase the complexity of fault diagnosis of the rotor system, which seriously threatens the safety and economy of nuclear power plants (NPPs). In order to accurately identify composite faults in the rotor system, a fault diagnosis method based on symmetrized dot pattern and residual neural networks is proposed. First, multiple sensors are used to collect vibration signals from the rotor system, and these signals are subsequently converted into multi-channel symmetrized dot pattern images to characterize the health status of the rotor system. Secondly, the deep residual neural network is constructed, and the self-attention mechanism is introduced to optimize the network to improve the diagnostic performance of the model. Finally, the residual neural network based on self-attention is used to recognize multi-channel symmetrized dot pattern images to achieve composite fault diagnosis of the rotor system. In the case study, the proposed method is applied to the fault simulation test bench, and performance evaluation is completed based on multiple indicators. The results show that the proposed method can diagnose composite faults of the rotor system with high accuracy, and its diagnostic performance is better than other cutting-edge methods, indicating its potential application value in the composite fault diagnosis task of the NPPs rotor system.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"211 ","pages":"Article 111029"},"PeriodicalIF":1.9,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143146676","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 neutronic comparative study of reflectors in radially and axially heterogeneous cores for the ABR-1000 sodium cooled fast reactor","authors":"Md. Hasebul Hasan Niloy ,&nbsp;Md. Tanvir Ahmed ,&nbsp;Farhana Islam Farha","doi":"10.1016/j.anucene.2024.111019","DOIUrl":"10.1016/j.anucene.2024.111019","url":null,"abstract":"<div><div>In continuation of previous research work, this study investigated the neutronic behavior of ABR-1000 using OpenMC simulations with nine different reflector materials in axial and radial core configurations. In this research, neutron leakage, energy spectrum, power distribution, flux &amp; fission distribution, isotope evolution, breeding ratio, sodium void reactivity worth, Doppler constant, and effective multiplication factor were evaluated for each model. The findings of this study indicated that BeO was the best reflector material in the axial model because it had the lowest neutron leakage (0.0517% at EOL), the highest fertile power fraction, and a more uniform flux distribution. However, PbO outperformed other reflectors in the radial model due to axial blanket placement, which resulted in maximum cycle length and the most negligible leakage (0.84335% at EOL). Insights on isotopic changes over time and neutronic behaviors were unveiled through this study, aiding in improved concepts of fast reactor designs.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"211 ","pages":"Article 111019"},"PeriodicalIF":1.9,"publicationDate":"2025-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143146511","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}