Annals of Nuclear Energy最新文献_第9页

Development and validation of fully-coupled subchannel analysis code for LMR within the MOOSE framework

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-01-18 DOI: 10.1016/j.anucene.2025.111199

Xinyang Zhu, Jinshun Wang, Ronghua Chen, Yuhang Niu, Yingwei Wu, Dalin Zhang, Wenxi Tian

{"title":"Development and validation of fully-coupled subchannel analysis code for LMR within the MOOSE framework","authors":"Xinyang Zhu, Jinshun Wang, Ronghua Chen, Yuhang Niu, Yingwei Wu, Dalin Zhang, Wenxi Tian","doi":"10.1016/j.anucene.2025.111199","DOIUrl":"10.1016/j.anucene.2025.111199","url":null,"abstract":"<div><div>As one of the Gen IV advanced reactors, liquid metal reactor (LMR) holds promising prospects for its high fuel efficiency and excellent inherent safety performance. Owing to its complex working conditions and ultra-high operating temperature, a thermal–hydraulic analysis of the reactor core is gradually playing a bigger role in recent years. Therefore, a subchannel code FLARE for LMRs has been developed within the Multiphysics Object-Oriented Simulation Environment (MOOSE) Framework, accompanied by the physical models tailored for LMRs embedded in FLARE.</div><div>Additionally, a hybrid discretization approach involving the Discontinuous Galerkin (DG) and Finite Element Method as well as the Jacobian-Free Newton-Krylov (JFNK) method are employed to solve the equations in a fully-coupled way. To validate the computational convergence of FLARE code under low flow rate conditions, the 7-pin experiment is adopted. The results exhibit that the absolute errors between the computed values and experimental data for the majority of calculation points are within 5 K. Furthermore, comparisons between the calculation values of FLARE (Fully-coupled transient code for Liquid-metal-cooled Advanced REactor), those of other programs and the experimental data are performed using 19-pin and 37-pin assembly experiments. The computational results indicate a good agreement between FLARE, experimental values, and other programs. In conclusion, FLARE code possesses the capability to accurately analyze the LMR core, which may provide new ideas for in-depth coupling research based on MOOSE.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"214 ","pages":"Article 111199"},"PeriodicalIF":1.9,"publicationDate":"2025-01-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143160466","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

High-dimensional multi-objective shielding optimization method based on multi-parameter shielding calculation agent model

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-01-17 DOI: 10.1016/j.anucene.2024.111182

Long Gui , Yingming Song , Weiwei Yuan , Yue Xia

{"title":"High-dimensional multi-objective shielding optimization method based on multi-parameter shielding calculation agent model","authors":"Long Gui , Yingming Song , Weiwei Yuan , Yue Xia","doi":"10.1016/j.anucene.2024.111182","DOIUrl":"10.1016/j.anucene.2024.111182","url":null,"abstract":"<div><div>The design of complex reactor shielding structures requires consideration of neutron and photon radiation levels in various regions, as well as trade-offs in weight, volume, and cost, leading to a substantial increase in shielding calculation parameters and optimization objectives. This study introduces a high-dimensional multi-objective shielding optimization method based on a multi-parameter shielding calculation surrogate model, with significant improvements to the FCNN-NSGAIII shielding optimization method which integrates a neural network with a genetic algorithm. For the optimization of complex reactor shielding structures under diverse source item energy spectra, the multi-parameter surrogate model achieves a prediction error reduction of an order of magnitude to 3.65% compared to traditional neural networks. Furthermore, the k_NSGAIII optimization algorithm, enhanced with a knee-point strategy, demonstrates a greater relative set coverage indicator than the NSGAIII algorithm, indicating its ability to identify superior shielding design schemes.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"214 ","pages":"Article 111182"},"PeriodicalIF":1.9,"publicationDate":"2025-01-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143160465","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

Design and analysis of a nuclear heating system integrated with molten salt energy storage

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-01-16 DOI: 10.1016/j.anucene.2025.111197

Hao-Fang Chong, Ruo-Jun Xue, Chen-Yang Gao, Guang-Liang Chen, Min-Jun Peng

引用次数: 0

Study on liquid phase separation phenomenon by constructing multi-physics field model

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-01-16 DOI: 10.1016/j.anucene.2025.111201

Kerong Guo , Houjun Gong , Rongpei Shi , Yuanfeng Zan , Yihui Guo , Xingjun Liu , Yanping Huang

{"title":"Study on liquid phase separation phenomenon by constructing multi-physics field model","authors":"Kerong Guo , Houjun Gong , Rongpei Shi , Yuanfeng Zan , Yihui Guo , Xingjun Liu , Yanping Huang","doi":"10.1016/j.anucene.2025.111201","DOIUrl":"10.1016/j.anucene.2025.111201","url":null,"abstract":"<div><div>After the core meltdown in a severe accident, the molten pool (corium) formed at the lower head of the pressure vessel occurs liquid phase separation phenomenon at high temperature, Corium’s morphologic evolution has a great influence on theIn-vessel retention technology. Therefore, the purpose of this study is to investigate the transient morphological evolution of the molten pool by coupling the thermodynamic properties of the corium, the flow and heat transfer characteristics. Firstly, considering the solidification effect, a multi-physics model with phase field − flow field − temperature field coupling is constructed to simulate the dynamic liquid phase separation phenomenon of the corium. Then it is verified that the phase-field model can be applied to macroscale simulation by using the U-O binary free energy for practical purposes. Also the morphological evolution and its kinetics of the U-O binary system, as well as the formation mechanism are discussed. The transient process of droplets nucleation, floating, fusion, and finally formation of stratified structure was observed, and the phenomenon of a ring of solid oxide wrapped around the liquid-phases was found. The results show that the constructed model can clearly capture the dynamic phenomenon in the process of liquid phase separation, and the model can be applied to the analysis of liquid phase separation of quaternary or multivariate systems, so as to provide a certain support for the safety analysis and design of reactors. It can also provide a reference for the analysis of liquid phase separation of complex materials.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"214 ","pages":"Article 111201"},"PeriodicalIF":1.9,"publicationDate":"2025-01-16","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143160463","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

Investigation of the impact of rotor- stator matching modes on the pressure pulsations of the guide vane centrifugal pump

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-01-15 DOI: 10.1016/j.anucene.2025.111189

Ning Zhang , Haozhe Dong , Fankun Zheng , Mona Gad , Delin Li , Bo Gao

{"title":"Investigation of the impact of rotor- stator matching modes on the pressure pulsations of the guide vane centrifugal pump","authors":"Ning Zhang , Haozhe Dong , Fankun Zheng , Mona Gad , Delin Li , Bo Gao","doi":"10.1016/j.anucene.2025.111189","DOIUrl":"10.1016/j.anucene.2025.111189","url":null,"abstract":"<div><div>The main source of intense pressure pulsation during the operation of a guide vane centrifugal pump is the rotor–stator interaction, which is directly related to the matching modes of the impeller and guide vane. In order to grasp the influence of different impeller/vane matching modes on the pump pressure pulsation, this study designs three different guide vanes and investigates the complex pressure pulsations through experimental tests. Besides, the complex internal flow structure of the pump is also explored based on the numerical computation means of DDES to reveal the typical flow field of this type of centrifugal pump. The findings of the experiment demonstrate that the blade passing frequency remains the dominant frequency in the pressure pulsation spectrum even under various rotor–stator matching modes. The DY8 and DY9 pumps are shown to be able to significantly reduce the pressure pulsation energy caused by rotor–stator interaction at the design and high flow conditions based on the amplitude of the blade passing frequency and the RMS value within the 0–1000 Hz frequency region. The impeller output surface forms a notable jet-wake flow pattern, as seen by the numerical findings, which also characterize the high and low flow zones. Both the guide vane and the impeller create typical vortical structures, and as the impeller rotates, the impeller’s vortex will interact with the guide vane. Choosing a larger number of guide vane blades during the pump design is advised in light of the decreased rotor–stator contact.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"214 ","pages":"Article 111189"},"PeriodicalIF":1.9,"publicationDate":"2025-01-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143160387","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

Measurement of the neutron and gamma spectra at the training and research reactor AKR-2

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-01-15 DOI: 10.1016/j.anucene.2025.111194

Marek Zmeškal , Michal Košťál , Marco Viebach , Carsten Lange , Zdeněk Matěj

{"title":"Measurement of the neutron and gamma spectra at the training and research reactor AKR-2","authors":"Marek Zmeškal , Michal Košťál , Marco Viebach , Carsten Lange , Zdeněk Matěj","doi":"10.1016/j.anucene.2025.111194","DOIUrl":"10.1016/j.anucene.2025.111194","url":null,"abstract":"<div><div>The reactor <span><math><mi>γ</mi></math></span>-ray spectrum is formed by superposition of various sources, namely <span><math><mi>γ</mi></math></span>-ray spectrum from neutron capture, inelastic scattering or other reactions with their characteristic discrete <span><math><mi>γ</mi></math></span> rays and a prompt fission <span><math><mi>γ</mi></math></span>-ray spectrum (PFGS) of fissile materials, which has only continuous component. The main discrete <span><math><mi>γ</mi></math></span> rays in thermal-neutron reactor have energies below 10 MeV. Due to this fact, one can assume that above 10 MeV the studied <span><math><mi>γ</mi></math></span>-ray spectrum is nearly identical with <sup>235</sup>U(n<span><math><msub><mrow></mrow><mrow><mtext>th.</mtext></mrow></msub></math></span>, fiss) PFGS, as <sup>235</sup>U fission causes more than 99.9 % of total fission in AKR-2. The measurement was performed with scintillation spectrometry using stilbene crystal 45 × 45 mm and newly developed and well validated gamma response matrix. The obtained spectrum is consistent with previous measurements performed in the LR-0 reactor and it is worth noting that a good agreement was reached with the new evaluation used in ENDFB-VIII.0 nuclear data library.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"214 ","pages":"Article 111194"},"PeriodicalIF":1.9,"publicationDate":"2025-01-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"143159454","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

Properties and characteristics of corium prototype of a fast power reactor

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-01-14 DOI: 10.1016/j.anucene.2025.111200

Nurzhan Mukhamedov, Ivan Kukushkin, Vladimir Vityuk, Galina Vityuk, Sergey Dolzhikov, Yerzhan Sapatayev

引用次数: 0

Study on the difference of internal flow in reactor coolant pump under high-temperature and high-pressure environment and normal temperature and pressure

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-01-14 DOI: 10.1016/j.anucene.2025.111198

Wang Haoshu , Jiang Xinshu , Zhang Wenjie , Zhi Yifan , Long Yun

引用次数: 0

A comparative analysis of uncertainty quantification using the deviation-based cost function

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-01-13 DOI: 10.1016/j.anucene.2025.111196

Shengli Chen, Shuyi Chen, Zhuo Li

引用次数: 0

Parallelization and application of SACOS-LMR for whole-core pin-by-pin thermal-hydraulic analysis in LMFRs

IF 1.9 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-01-13 DOI: 10.1016/j.anucene.2024.111177

Jinshun Wang , Ronghua Chen , Sicong Xiao , Xinyang Zhu , Minyang Gui , Wenxi Tian , Suizheng Qiu

引用次数: 0