Annals of Nuclear Energy最新文献_第3页

Cell-wise static coupling calculation of a new neutronics/thermal-hydraulics coupling benchmark for plate-type PWR core 板式压水堆堆芯新型中子/热工-水力学耦合基准的单元静态耦合计算

IF 2.3 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-09-23 DOI: 10.1016/j.anucene.2025.111895

Zhigang Li , Junjie Pan , Shanfang Huang , Yingwei Wu , Xiafeng Zhou , Wei Lu , Bangyang Xia , Wei Zeng , Shenglong Qiang

{"title":"Cell-wise static coupling calculation of a new neutronics/thermal-hydraulics coupling benchmark for plate-type PWR core","authors":"Zhigang Li , Junjie Pan , Shanfang Huang , Yingwei Wu , Xiafeng Zhou , Wei Lu , Bangyang Xia , Wei Zeng , Shenglong Qiang","doi":"10.1016/j.anucene.2025.111895","DOIUrl":"10.1016/j.anucene.2025.111895","url":null,"abstract":"<div><div>To support the verification of cell-wise neutronics/thermal hydraulics (N-TH) coupling codes for Pressurized Water Reactor (PWR), the Nuclear Power Institute of China (NPIC) collaborated with multiple research institutions in the nuclear energy field to design and develop COPHP, a high-parameter PWR full core cell-wise N-TH coupling benchmark. This paper elaborates on Part II of the benchmark—cell-wise static N-TH coupling—including case design, modeling, results, and deviation analysis. Key conclusions are as follows: 1) Consistency was observed among the results from four participating codes (RMC/CORTH-R, OpenMC, CORCA-SPn/CORTH-R, and CORCA-SPn/TH1D) across 32 cases covering two core configurations. 2) Compared to RMC/CORTH-R: OpenMC exhibited a maximum <em>k<sub>eff</sub></em> deviation of −29.6 pcm and a maximum cell-wise power weighting error (PWE) of 0.185 %; CORCA-SPn/CORTH-R showed a maximum <em>k<sub>eff</sub></em> deviation of −474.6 pcm and a maximum PWE of 3.179 %; CORCA-SPn/TH1D yielded a maximum <em>k<sub>eff</sub></em> deviation of 1310.4 pcm and a maximum PWE of 5.245 %. 3) Two-phase flow at the core outlet in some cases of COPHP-B significantly affected the N-TH coupling results of CORCA-SPn/TH1D. 4) This benchmark suite provides comprehensive results for high-fidelity N-TH coupling in high-parameter PWRs, catering to diverse validation needs.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"226 ","pages":"Article 111895"},"PeriodicalIF":2.3,"publicationDate":"2025-09-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145109119","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

Automatic generation control of a nuclear-renewable hybrid power system using optimal PID controller 基于最优PID控制器的核能-可再生能源混合电力系统自动发电控制

IF 2.3 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-09-22 DOI: 10.1016/j.anucene.2025.111874

Md. Rahat Khan , Abid Hossain Khan , Ying Yin Tsui , Md. Zahurul Islam

引用次数: 0

Analysis of the continuous operational characteristics of the control rod eddy current retarder 控制棒涡流缓速器连续工作特性分析

IF 2.3 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-09-22 DOI: 10.1016/j.anucene.2025.111888

Hongyu Wu, He Yan, Yujie Dong, Xingzhong Diao

{"title":"Analysis of the continuous operational characteristics of the control rod eddy current retarder","authors":"Hongyu Wu, He Yan, Yujie Dong, Xingzhong Diao","doi":"10.1016/j.anucene.2025.111888","DOIUrl":"10.1016/j.anucene.2025.111888","url":null,"abstract":"<div><div>The control rod eddy current retarder (CRECR) serves as the primary damping device during the control rod dropping process in the high temperature gas-cooled reactor, converting the gravitational potential energy into eddy current losses inside the conductor disk of CRECR. In order to analyze the torque performance of CRECR during continuous operation, a multi-node coupling method for electromagnetic and thermal simulation was proposed, and an electromagnetic-thermal coupling simulation model was established. Subsequently, the model was experimentally verified and the influence of speed, operating time and compensation claddings were analyzed. The torque deviation remains consistently below 7 % within 300 s. Additionally, continuous operation at speeds exceeding 300 rpm resulted in non-ignorable changes in component temperature and torque, necessitating careful consideration in engineering tests. Furthermore, a torque rebound phenomenon was observed during continuous operation, indicating that using compensation claddings can effectively mitigate the impact of thermal fade and improve the torque stability.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"226 ","pages":"Article 111888"},"PeriodicalIF":2.3,"publicationDate":"2025-09-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145109122","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 unified surrogate model for enhanced photon shielding through an all-natural-element multi-group flux dataset 基于全自然元素多群通量数据集的增强光子屏蔽统一代理模型

IF 2.3 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-09-20 DOI: 10.1016/j.anucene.2025.111887

Junyi Chen, Chenghao Cao, Shaoning Shen, Tianyuan Guo, Jingang Liang

{"title":"A unified surrogate model for enhanced photon shielding through an all-natural-element multi-group flux dataset","authors":"Junyi Chen, Chenghao Cao, Shaoning Shen, Tianyuan Guo, Jingang Liang","doi":"10.1016/j.anucene.2025.111887","DOIUrl":"10.1016/j.anucene.2025.111887","url":null,"abstract":"<div><div>Efficient gamma shielding analysis is vital for nuclear safety. However, traditional Point Kernel approaches relying on outdated ANSI databases face significant limitations in providing comprehensive and fine-grained shielding analysis. This study addresses this by creating a detailed multi-group photon flux dataset for 92 nuclides via Monte Carlo simulations. The dataset’s complexity renders traditional modeling techniques ineffective. We introduce a novel generative-reconstruction surrogate model, combining a conditional Generative Adversarial Network (cGAN) and a fine-tuned UNet, both enhanced with self-attention mechanisms. This model predicts complex multi-group photon shielding parameter fields. Verification shows the model accurately predicts parameter fields, with 95% of samples achieving an average relative deviation below 20%. Predicted relative flux, converted to buildup factors, aligns well with Monte Carlo truth and ANSI values, confirming reliability and improved conservatism. This approach offers an efficient, accurate alternative for photon shielding calculations, proposing a new approach for data and computation.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"226 ","pages":"Article 111887"},"PeriodicalIF":2.3,"publicationDate":"2025-09-20","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145099862","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 of a MC/MOC two-step method for sodium fast reactor analysis with transport-corrected flux-moment multigroup cross-section generation method 基于输运修正通量矩多群截面生成法的钠快堆MC/MOC两步法研究

IF 2.3 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-09-19 DOI: 10.1016/j.anucene.2025.111853

Yiwei Wu , Qufei Song , Yuyang Shen , Hui Guo , Yao Xiao , Hanyang Gu

{"title":"Development of a MC/MOC two-step method for sodium fast reactor analysis with transport-corrected flux-moment multigroup cross-section generation method","authors":"Yiwei Wu , Qufei Song , Yuyang Shen , Hui Guo , Yao Xiao , Hanyang Gu","doi":"10.1016/j.anucene.2025.111853","DOIUrl":"10.1016/j.anucene.2025.111853","url":null,"abstract":"<div><div>New fast reactor designs could feature complex geometries and axial heterogeneity. The MC/MOC two-step method has the advantage of the high adaptability of Monte Carlo (MC) and Method of Characteristics (MOC) to geometry, offering a precise solution for such reactors. However, limited studies exist on applying the MOC method to 3D sodium fast reactors. MC-generated multi-group cross-sections, which ignore the anisotropy with respect to neutron direction, introduce bias in transport calculations. This paper develops a two-step MC/MOC approach, integrating the direct 3D MOC method and the Transport-corrected flux-moment homogenization technique (TC-MHT) for 3D reactor problems. The scheme is verified on the sodium-cooled fast reactor MET-1000, the results confirm the feasibility of the method for both homogeneous and heterogeneous core geometries. The TC-MHT method significantly reduces calculation bias, with eigenvalue bias below 200 pcm, heterogeneous pin power bias under 3.1%, and homogeneous assembly power bias under 1.4%.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"226 ","pages":"Article 111853"},"PeriodicalIF":2.3,"publicationDate":"2025-09-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145099858","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

General intrusive neutron transport reduced-order model applicable to various deterministic methods 一般侵入中子输运降阶模型适用于各种确定性方法

IF 2.3 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-09-19 DOI: 10.1016/j.anucene.2025.111854

Honghang Chi, Yongshi Li, Yuchen Xie, Yahui Wang, Yu Ma

引用次数: 0

Reliability analysis of a lead-bismuth cooled passive system based on AL-I surrogate model 基于AL-I替代模型的铅铋冷却被动系统可靠性分析

IF 2.3 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-09-19 DOI: 10.1016/j.anucene.2025.111875

Feiyang Li , Youwei Zeng , Pengcheng Zhao , Zijing Liu , Wei Li

{"title":"Reliability analysis of a lead-bismuth cooled passive system based on AL-I surrogate model","authors":"Feiyang Li , Youwei Zeng , Pengcheng Zhao , Zijing Liu , Wei Li","doi":"10.1016/j.anucene.2025.111875","DOIUrl":"10.1016/j.anucene.2025.111875","url":null,"abstract":"<div><div>Passive residual heat removal systems ensure the safe operation of lead–bismuth fast reactors. However, the resistance of such systems is similar to natural driving forces, while small fluctuations in the surrounding environment and material parameters can cause system failure; thus, analyzing the reliability of passive residual heat removal systems is important for lead–bismuth cooling. This study utilizes the passive system in the lead–bismuth eutectic loop of the TALL-3D experimental facility and proposes a reliability analysis based on the active learning-integration (AL-I) surrogate model. The AL-I surrogate model is constructed first, and single-failure and multiple-failure region validations are performed to ensure accuracy and robustness of the model. Subsequently, the sensitivity and reliability of the TALL-3D non-energetic system is determined. The active learning ensemble surrogate model only needs 99 low-cost numerical calculations to obtain a reliable result with a failure rate of 0.0650%. This model not only significantly reduces the computational resources and time costs, but also allows high-precision failure probability assessments. Therefore, this study shows that the AL-I surrogate model is advantageous for lead–bismuth cooled non-energetic waste heat discharge systems and offers solid technical support for engineering such systems.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"226 ","pages":"Article 111875"},"PeriodicalIF":2.3,"publicationDate":"2025-09-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145099859","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

FCMI analysis of multiphysics coupling of fuel rods at the end of cycle of Xi’an pulsed reactor 西安脉冲堆循环末期燃料棒多物理场耦合的FCMI分析

IF 2.3 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-09-19 DOI: 10.1016/j.anucene.2025.111867

Zhaohao Wang , Jinkai Zhang , Tianliang Hu , Di Yun , Duoyu Jiang , Da Li , Lixin Chen , Wenbo Liu

{"title":"FCMI analysis of multiphysics coupling of fuel rods at the end of cycle of Xi’an pulsed reactor","authors":"Zhaohao Wang , Jinkai Zhang , Tianliang Hu , Di Yun , Duoyu Jiang , Da Li , Lixin Chen , Wenbo Liu","doi":"10.1016/j.anucene.2025.111867","DOIUrl":"10.1016/j.anucene.2025.111867","url":null,"abstract":"<div><div>The Xi’an Pulse Reactor (XAPR), being a small-scale experimental reactor, operates within a very complex environment. Consequently, accurate estimation of neutron-thermo-mechanical coupling of the fuel is a crucial step to prevent operation, particularly pulse operation, outside fuel thermo-mechanical safety margin. To obtain precise temperature and stress distributions within the XAPR, a loosely coupled approach based on the finite element method was employed. In the present work, neutron transport equations were calculated using OpenMC, and the Multiphysics Object-Oriented Simulation Environment (MOOSE), an open-source multi-physics coupling platform, was employed for heat transfer and mechanics calculations. The physical modules have also been verified by comparing calculation results against corresponding experimental data, confirming the reliability of the performed calculations. In addition, we conducted 3-dimensional (3-D) calculations of the bending effects of fuel rods due to Pellet-Clad Mechanical Interaction (PCMI) under different operating conditions and discussed the influence of different pulse state initiation time on the bending of the fuel.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"226 ","pages":"Article 111867"},"PeriodicalIF":2.3,"publicationDate":"2025-09-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145099861","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

Modeling and analysis of electromagnetic, fluid and energy characteristics in flat linear induction pump 平板线性感应泵的电磁、流体和能量特性建模与分析

IF 2.3 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-09-19 DOI: 10.1016/j.anucene.2025.111841

Sixian Zhu , Jien Ma , Zheng Wang , Keming Bi , Xin Yan , Youtong Fang

引用次数: 0

An implicit numerical method for the three-dimensional two-fluid model with large phase changes in pressurized water reactors 压水堆三维大相变双流体模型的隐式数值计算方法

IF 2.3 3区工程技术

Annals of Nuclear Energy Pub Date : 2025-09-18 DOI: 10.1016/j.anucene.2025.111873

Na Young Song, Han Young Yoon

{"title":"An implicit numerical method for the three-dimensional two-fluid model with large phase changes in pressurized water reactors","authors":"Na Young Song, Han Young Yoon","doi":"10.1016/j.anucene.2025.111873","DOIUrl":"10.1016/j.anucene.2025.111873","url":null,"abstract":"<div><div>An implicit numerical method is proposed for solving the three-dimensional two-fluid model with a large phase, which is widely used in two-phase flow analysis of Pressurized Water Reactors (PWRs). The phase change process is implicitly modeled by coupling it with the pressure equation derived from the momentum and mass conservation equations. Simultaneously, the convection and diffusion terms of the governing equations are treated implicitly. To reduce the size of the system matrix, the computation procedure is divided into two separate steps: the “phase-link” step and the “space-link” step. This implicit scheme has been implemented in CUPID, a three-dimensional two-phase flow analysis code developed specifically for PWR applications. The present method was verified using a conceptual problem that simulates two-phase flow blowdown and refill phenomena occurring during a Loss of Coolant Accident (LOCA). The calculations demonstrated stability even with a large Courant–Friedrichs–Lewy (CFL) number. Subsequently, the implicit scheme was validated against the FLECHT-SEASET reflood experiment. The robustness and accuracy of the implicit scheme were confirmed by comparing the simulation results with experimental data across different CFL numbers. The differences between the results obtained at various CFL numbers were negligible.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"226 ","pages":"Article 111873"},"PeriodicalIF":2.3,"publicationDate":"2025-09-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"145099850","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