Annals of Nuclear Energy最新文献

Development of a two-phase flow solver with two-fluid model based on OpenFOAM: Validation against two-phase boiling flow

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-25 DOI: 10.1016/j.anucene.2025.111491

Wenqiang Wu , Tao Huang , Peng Du , Zhenyu Feng , Dalin Zhang , Lei Zhou , Gongle Song , Jian Deng , Zhifang Qiu , Wenxi Tian , Suizheng Qiu , Guanghui Su

{"title":"Development of a two-phase flow solver with two-fluid model based on OpenFOAM: Validation against two-phase boiling flow","authors":"Wenqiang Wu , Tao Huang , Peng Du , Zhenyu Feng , Dalin Zhang , Lei Zhou , Gongle Song , Jian Deng , Zhifang Qiu , Wenxi Tian , Suizheng Qiu , Guanghui Su","doi":"10.1016/j.anucene.2025.111491","DOIUrl":"10.1016/j.anucene.2025.111491","url":null,"abstract":"<div><div>The continuous advancement in computer technology and mathematical-physical models has significantly propelled the development of numerical reactor technology. There is a growing focus on high-fidelity, multi-scale, and multi-physics coupling within a unified framework. OpenFOAM, based on the finite volume method, has emerged as a promising tool for addressing this challenge. This study explores its capabilities in system-level scales, successfully developing a two-fluid, six-equation solver. The realistic closure models cover flow and heat transfer scenarios within vertical channels under pre-CHF conditions. A virtual thermal structure accounts for conjugate heat transfer between the fluid and the solid. Furthermore, the solver adheres to the discretization and solution principles within the OpenFOAM framework. The developed solver has been extensively validated against experimental data for two-phase boiling flow, with results showing good agreement, thereby demonstrating the solver’s success. This work builds upon previous efforts involving the drift-flux solver and indicates that OpenFOAM can effectively handle one-dimensional or system-level scale calculations. It provides robust support for future endeavors in multi-scale and multi-physics coupling technologies.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"220 ","pages":"Article 111491"},"PeriodicalIF":1.9,"publicationDate":"2025-04-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143868606","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}

引用次数: 0

A review of research on melt and coolant interaction under different injection modes

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-25 DOI: 10.1016/j.anucene.2025.111495

Wenshu Jiang, Shuhua Zhou, Shuo Wang, Ruizhi Hao, Tao Lu

{"title":"A review of research on melt and coolant interaction under different injection modes","authors":"Wenshu Jiang, Shuhua Zhou, Shuo Wang, Ruizhi Hao, Tao Lu","doi":"10.1016/j.anucene.2025.111495","DOIUrl":"10.1016/j.anucene.2025.111495","url":null,"abstract":"<div><div>The interaction of high-temperature melt with coolant, also known as fuel–coolant interaction (FCI) or coolant-coolant interaction (CCI), should be considered one of the crucial factors causing devastation in nuclear reactor accidents. Based on different accident scenarios, the interaction modes between melt and coolant can be categorized into the melt-injection (MI) mode and the coolant-injection (CI) mode. In previous research, performing visualization experiments of the CI mode was challenging due to the opacity of metals. Considering that the CI mode is geometrically opposite to the MI mode, it is promising to obtain the fundamental interaction mechanisms of the CI mode from the research on the MI mode. Therefore, this review systematically summarizes the essential theories, prevailing experiments, and simulations of melt-coolant interaction according to the different interaction modes, focusing on the thermodynamic and hydrodynamic interaction processes, as well as current hotspots and challenges. Its core significance is to analyze melt-coolant interaction from the opposite processes of the CI mode and the MI mode, which could provide a new perspective for the research of the CI mode. Meanwhile, this review offers valuable insights for the subsequent research directions of melt-coolant interaction, such as optimizing empirical parameters in existing theoretical models and developing corresponding interfacial heat transfer model and the thermal expansion model of vapor explosions, which is crucial for predicting the potential risk of nuclear reactor accidents.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"220 ","pages":"Article 111495"},"PeriodicalIF":1.9,"publicationDate":"2025-04-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143874171","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}

引用次数: 0

Development and benchmarking of a point detector in OpenMC

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-25 DOI: 10.1016/j.anucene.2025.111497

Itay Horin , Or Alon , Arik Kreisel , Tsviki Y. Hirsh , Tamar Dayan , Hallel Fuks

引用次数: 0

Development of a new onset of film boiling model within the fouling layer

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-25 DOI: 10.1016/j.anucene.2025.111488

Xiaowen Wang , Maolong Liu , Rui Zhang , Tenglong Cong , Yao Xiao , Hanyang Gu

引用次数: 0

Radioisotope production at the advanced test reactor: process and lessons learned

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-24 DOI: 10.1016/j.anucene.2025.111463

Andrew Zillmer, Clinton Wilson, Jill Mitchell, Austen Fradeneck, Ryan Marlow, Erik Rosvall, William Green, Justin Lower

引用次数: 0

A review on nuclear emergency preparedness and response management

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-24 DOI: 10.1016/j.anucene.2025.111492

Yipeng Fan , Xiya Zhu , Jun Yang , Hongyun Xie

{"title":"A review on nuclear emergency preparedness and response management","authors":"Yipeng Fan , Xiya Zhu , Jun Yang , Hongyun Xie","doi":"10.1016/j.anucene.2025.111492","DOIUrl":"10.1016/j.anucene.2025.111492","url":null,"abstract":"<div><div>Emergency preparedness and response (EPR) are essential to protect the public health and environmental safety in the event of a nuclear or radiological emergency. In the paper, the fundamental concepts, framework and methods for nuclear and radiological emergency management are reviewed from a comprehensive perspective. Prior to the emergency classifications, the organizational framework, responsibilities and initiative programs especially undertaken by the International Atomic Energy Agency (IAEA) is literally introduced. Then the generic principles for classification of emergency planning zones (EPZ) and emergency action levels (EALs) are in detail discussed as a basis for the planning of protective actions that the national authorities and international agencies need to perform during a nuclear or radiological emergency. Meanwhile, the methodologies and tools used for radionuclides release, transport, dispersion and deposition, dose assessment are also systematically investigated and compared to provide a guide for practitioner’s research and vision in emergency preparedness planning. Finally, the major challenges and development trends associated with emergency preparedness and response are prospected with the revolution of edge artificial intelligence (AI-driven) solutions to leverage collaborative perception and risk-informed decision making in nuclear and radiological emergency management.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"219 ","pages":"Article 111492"},"PeriodicalIF":1.9,"publicationDate":"2025-04-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143863596","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}

引用次数: 0

Three-dimensional refined burnup characteristics analysis of Helical Cruciform Fuel

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-23 DOI: 10.1016/j.anucene.2025.111505

Qianni Duan , Wei Li , Kun Zhang , Junmei Wu , Zhifeng Li

{"title":"Three-dimensional refined burnup characteristics analysis of Helical Cruciform Fuel","authors":"Qianni Duan , Wei Li , Kun Zhang , Junmei Wu , Zhifeng Li","doi":"10.1016/j.anucene.2025.111505","DOIUrl":"10.1016/j.anucene.2025.111505","url":null,"abstract":"<div><div>The Helical Cruciform Fuel (HCF) is an advanced Innovative Fuel Design (IFD) that present greater challenges for three-dimensional(3D) refined burnup characteristic analysis. A burnup region division method for HCF was proposed and the burnup characteristic analysis was conducted using OpenMC code. 3D refined distribution of thermal and fast neutron flux and power density, isotope densities of typical nuclides at different positions of HCF were calculated. The influences of twist pitch, axial enrichment, and boundary conditions were studied. Meanwhile, burnup characteristic on HCF and cylindrical fuel was compared with the same material and volume. The results show that, the chain reaction of HCF can last longer, and has obvious economic advantages than cylinder fuel. Unlike cylindrical fuel, the circumferential distribution of neutron physical variables for HCF is inhomogeneous and becomes more pronounced with burnup. The proposed analysis method is applicable to any specially shaped fuel and effectively predicts the neutron physical properties during burnup, forming the foundation for IFD and safety analysis.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"219 ","pages":"Article 111505"},"PeriodicalIF":1.9,"publicationDate":"2025-04-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143860738","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}

引用次数: 0

A method fusing self-attention-SPN and NSGA-III for multi-objective radiation shielding design optimization

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-23 DOI: 10.1016/j.anucene.2025.111507

Li He , Guangyao Sun , Yican Wu

{"title":"A method fusing self-attention-SPN and NSGA-III for multi-objective radiation shielding design optimization","authors":"Li He , Guangyao Sun , Yican Wu","doi":"10.1016/j.anucene.2025.111507","DOIUrl":"10.1016/j.anucene.2025.111507","url":null,"abstract":"<div><div>High-performance compact nuclear facilities require radiation shielding designs that balance safety and weight considerations. Current intelligent shielding design methods typically combine Evolutionary Algorithms (EA) for optimization with neural networks for evaluation. However, the neural networks used, primarily BP or DNN models composed of Fully Connected (FC) layers, require large datasets and extensive computation resources. A novel method fusing Self-Attention-based Sequence Prediction Network (Self-Attention-SPN) and Non-dominated Sorting Genetic Algorithm III (NSGA-III) was proposed in this paper for multi-objective radiation shielding design optimization. By reformulating dose rate calculation as a sequence prediction problem, the SPN of lightweight network structure leverages the multi-physics feature projection and multi-head self-attention mechanism to effectively capture the inter-layer physical feature relationships, ensuring high prediction accuracy with small datasets. The method is validated using the Savannah reactor case, where SPN achieves Monte Carlo (MC)-level accuracy with significantly reduced computational cost. Comparative experiments show that training data with additional physical parameters can reduce SPN training loss, underscoring the importance of physical information. Furthermore, SPN outperforms BP in prediction accuracy, validating the effectiveness of the multi-head self-attention mechanism. Sensitivity analysis of NSGA-III coupled with SPN prediction perturbation confirms the robustness of the proposed method. The optimization solutions effectively converge to the Pareto front, demonstrating the method’s efficiency and reliability for multi-objective radiation shielding design.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"219 ","pages":"Article 111507"},"PeriodicalIF":1.9,"publicationDate":"2025-04-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143863597","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}

引用次数: 0

Cluster-dynamics study on the evolution of dislocation loops in molybdenum: The role of defect diffusion coefficient and equilibrium concentration

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-23 DOI: 10.1016/j.anucene.2025.111468

Teng Xie, Xinhua Yan, Menglu Qin, Lu Sun, Zhenfeng Tong

{"title":"Cluster-dynamics study on the evolution of dislocation loops in molybdenum: The role of defect diffusion coefficient and equilibrium concentration","authors":"Teng Xie, Xinhua Yan, Menglu Qin, Lu Sun, Zhenfeng Tong","doi":"10.1016/j.anucene.2025.111468","DOIUrl":"10.1016/j.anucene.2025.111468","url":null,"abstract":"<div><div>A cluster dynamics simulation based on rate theory was conducted to investigate the evolution of irradiation-induced dislocation loops in pure molybdenum (<span><math><mi>Mo</mi></math></span>) irradiated with <span><math><mrow><mn>30</mn><mspace></mspace><mi>keV</mi></mrow></math></span> <span><math><mi>He</mi></math></span><sup>+</sup> at <span><math><mrow><mn>673</mn><mspace></mspace><mi>K</mi></mrow></math></span>. The changes in number density and size of dislocation loops were analyzed, revealing rapid saturation of loop density with increasing dose, while the average loop radius grows and stabilizes at a maximum size. During the initial irradiation stage, significant nucleation leads to a rapid increase in loop density. The simulation results align well with in-situ transmission electron microscopy observations and clarify the kinetic mechanisms underlying key experimental features. It was found that the diffusion coefficients and thermal equilibrium concentrations of interstitial atoms and vacancies play critical roles in determining the evolution of loop density and size at elevated temperatures. This study provides insight into the microstructural evolution of irradiated molybdenum under helium ion exposure.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"219 ","pages":"Article 111468"},"PeriodicalIF":1.9,"publicationDate":"2025-04-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143863454","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}

引用次数: 0

Transport-corrected flux-moment homogenization method for generating P0 multigroup cross-section based on continuous energy Monte-Carlo

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-04-23 DOI: 10.1016/j.anucene.2025.111448

Yuyang Shen , Yiwei Wu , Qufei Song , Kuaiyuan Feng , Hui Guo , Hanyang Gu

{"title":"Transport-corrected flux-moment homogenization method for generating P0 multigroup cross-section based on continuous energy Monte-Carlo","authors":"Yuyang Shen , Yiwei Wu , Qufei Song , Kuaiyuan Feng , Hui Guo , Hanyang Gu","doi":"10.1016/j.anucene.2025.111448","DOIUrl":"10.1016/j.anucene.2025.111448","url":null,"abstract":"<div><div>The scattering anisotropy multigroup cross-section (MGXS) with respect to the outgoing angle, as well as the anisotropy of the total MGXS with respect to the incident angle, are critical for generating high-precision MGXS used in transport core calculations. A TC-MHT method based on continuous energy Monte-Carlo is developed to generate high-accuracy P<sub>0</sub> MGXS. This method addresses scattering anisotropy using transport correction (TC) and handles the anisotropy of total cross-section through the flux-moment homogenization technique (MHT). This method is validated using the Megapower benchmark. In reactivity calculations, the bias is decomposed and the reasons for the bias are analyzed. The bias is reduced to less than 160 pcm by using the TC-MHT method. For calculations of control drum worth, the bias does not exceed 0.2%. In power calculations, the maximum pin-by-pin power distribution deviation is within 4%. This demonstrates that TC-MHT method can generate high-precision, highly adaptable MGXS for deterministic code.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"219 ","pages":"Article 111448"},"PeriodicalIF":1.9,"publicationDate":"2025-04-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143860726","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}

引用次数: 0