Progress in Nuclear Energy最新文献_第10页

A review of research on liquid-metal-cooled reactor and supercritical carbon dioxide Brayton cycle coupled system 液态金属冷却堆与超临界二氧化碳布雷顿循环耦合系统的研究进展

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-08-06 DOI: 10.1016/j.pnucene.2025.105957

Zhengyu Gong , Yaolei Zou , Songbai Cheng , Bing Tan , Pengcheng Zhao

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Drop size distribution and dispersed phase hold up in a continuous pump-mix mixer with trapezoidal blade impeller 梯形叶片叶轮连续泵-混合器中液滴的粒径分布和分散相保持

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-08-06 DOI: 10.1016/j.pnucene.2025.105931

Nirvik Sen , A.U. Renjith , K.K. Singh , K.T. Shenoy

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Examining lessons learned from the COVID-19 response to inform nuclear emergency management 审查2019冠状病毒病应对经验教训，为核应急管理提供信息

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-08-04 DOI: 10.1016/j.pnucene.2025.105959

Dev Minotra

{"title":"Examining lessons learned from the COVID-19 response to inform nuclear emergency management","authors":"Dev Minotra","doi":"10.1016/j.pnucene.2025.105959","DOIUrl":"10.1016/j.pnucene.2025.105959","url":null,"abstract":"<div><div>Decision makers and public health officials in public health emergencies are faced with multiple challenges including uncertain information, incomplete information, pressures from the public, to name a few. When faced with time pressure, these factors can lead to poor decisional outcomes. As there are a number of parallels between the COVID-19 pandemic response and nuclear emergency management, this study extracts lessons learned and other insights from the COVID-19 pandemic to inform decision makers with roles in nuclear emergency management. Five subject-matter experts who had critical roles during the COVID-19 response within Canada were interviewed in this study. The study shows that to make effective decisions, emergency management organizations should build and maintain awareness about local communities and vulnerable groups that may be impacted by an emergency. They also need decision support tools to quantify socio-economic and mental health impacts of all public health interventions. The paper presents other recommendations applicable in the preparatory and response phases of emergency management, which include conducting exercises with bias-inducing injects, communicating unknowns and being transparent with the public, ensuring consistency across messages, considering long-term impacts of decisions such as fatigue, maintaining awareness of public perspectives, delivering effective messages, and countering misinformation. Many of these considerations are aimed at providing balanced perspectives in decision making, which may reduce the likelihood of bias.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"190 ","pages":"Article 105959"},"PeriodicalIF":3.2,"publicationDate":"2025-08-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144771549","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}

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High-fidelity microreactor load follow simulations with model predictive control 采用模型预测控制的高保真微反应器负荷跟踪仿真

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-08-02 DOI: 10.1016/j.pnucene.2025.105889

Sooyoung Choi , Qicang Shen , Changho Lee , Claudio Filippone , Brendan Kochunas

{"title":"High-fidelity microreactor load follow simulations with model predictive control","authors":"Sooyoung Choi , Qicang Shen , Changho Lee , Claudio Filippone , Brendan Kochunas","doi":"10.1016/j.pnucene.2025.105889","DOIUrl":"10.1016/j.pnucene.2025.105889","url":null,"abstract":"<div><div>This paper presents the application of an Model Predictive Control (MPC) controller for the autonomous load-follow operation of a High-Temperature Gas-Cooled Reactor (HTGR)-type microreactor. The study enhances the reliability of the simulation by utilizing the high-fidelity neutronics code, PROTEUS, as the actual plant model. The Simplified Thermal Hydraulics/Fluids (STH) solver and control drum decusping methods have been integrated into PROTEUS. Additionally, a reduced-order model based on the point kinetics equations and lumped Thermal Hydraulics/Fluids (TH) models has been developed for integration with the MPC controller. An adaptive MPC is used to compute the control input required to follow a given power scenario, enhancing accuracy by sequentially linearizing the nonlinear reduced-order model for optimization. Numerical results from the PROTEUS/MPC code system for the load-follow operation of a 3D microreactor at a ramp rate of 20% per minute show that the tracking power error is minimal, remaining under 0.234%, and the control inputs stay within predetermined constraints. In-depth sensitivity tests on the parameters used in the MPC controller and reduced-order model further verify the robustness and flexibility of the MPC controller.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"189 ","pages":"Article 105889"},"PeriodicalIF":3.2,"publicationDate":"2025-08-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144756990","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}

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Analysis of nitrogen intrusion from ECCS accumulators in SBLOCA scenarios at LSTF test facility LSTF试验装置SBLOCA工况下ECCS蓄能器氮侵入分析

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-08-01 DOI: 10.1016/j.pnucene.2025.105954

Tomás Ten-Gallardo , Sergio Gallardo , María Lorduy-Alós , Gumersindo Verdú

{"title":"Analysis of nitrogen intrusion from ECCS accumulators in SBLOCA scenarios at LSTF test facility","authors":"Tomás Ten-Gallardo , Sergio Gallardo , María Lorduy-Alós , Gumersindo Verdú","doi":"10.1016/j.pnucene.2025.105954","DOIUrl":"10.1016/j.pnucene.2025.105954","url":null,"abstract":"<div><div>After the injection of borated water during accidental sequences, the intrusion of nitrogen gas from the accumulators once emptied can degrade heat transfer mechanisms and thus hinder core cooling. The non-condensable gas that enters the cold legs transfers and accumulates in the U-tubes of the steam generators and their outlet plenums. This can cause flow stagnation and even prevent reflux cooling. Furthermore, a temporary and fluctuating increase in primary pressure may occur, disabling the low-pressure injection system pumps to restore the inventory. In this scenario, it is essential to confirm the effectiveness of the accident management measures under the influence of non-condensable gas. To date, several experimental studies have been conducted within the framework of OECD/NEA programs at experimental facilities such as LSTF, PKL, or ATLAS (all related to PWR-type designs) where the issue of non-condensable gas intrusion has been studied, but always as a secondary objective of the analyzed sequences. In this work, three SBLOCA in the reactor pressure vessel of the LSTF facility are analyzed to determine the effect of nitrogen intrusion in the primary system. For calculations, the thermal-hydraulic code TRACE5 patch 5 is used. Results include the evolution of the main thermal-hydraulic parameters (pressures, mass flow rates and temperatures) and sensitivity cases for different scenarios of nitrogen intrusion. Based on the analysis of three experiments, it can be concluded that while nitrogen accumulation in the U-tubes is a common effect, the activation of safety systems such as LPIS depends on the location, size of the break and action management measures.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"189 ","pages":"Article 105954"},"PeriodicalIF":3.2,"publicationDate":"2025-08-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144750037","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}

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Deep cascade utilization of nuclear residual heat: A hybrid approach combining thermodynamic analysis and pattern recognition 核余热的深度级联利用：一种结合热力学分析和模式识别的混合方法

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-07-31 DOI: 10.1016/j.pnucene.2025.105946

Dong Zhang , Yiran Li , Haochun Zhang

{"title":"Deep cascade utilization of nuclear residual heat: A hybrid approach combining thermodynamic analysis and pattern recognition","authors":"Dong Zhang , Yiran Li , Haochun Zhang","doi":"10.1016/j.pnucene.2025.105946","DOIUrl":"10.1016/j.pnucene.2025.105946","url":null,"abstract":"<div><div>The efficient utilization of nuclear residual heat remains a critical challenge for enhancing the energy, economic, and environmental performance of nuclear power plants. Addressing this, the present study proposes a hybrid approach that combines advanced thermodynamic analysis with pattern recognition techniques to analyze and optimize the deep cascade utilization of nuclear waste heat. An integrated system is developed, incorporating the sCO<sub>2</sub> Brayton cycle, an ammonia-water absorption heat pump (AHP), and an ejector refrigeration cycle, to convert waste heat into heating, cooling, and power. Thermodynamic performance is assessed using the first and second laws of thermodynamics, with results indicating net work output, cooling capacity, and heating capacity of 203,901.37 kW, 333,758.08 kW, and 32,817.04 kW, respectively. The system achieves a thermal efficiency of 34.15 %, an exergy efficiency of 47.29 %, with the sCO<sub>2</sub> Brayton cycle contributing 78.61 % of the total exergy destruction. Complementing the thermodynamic analysis, pattern recognition techniques, including the Self-Organizing Map (SOM) and Global Sensitivity Analysis (GSA), are employed to identify key parameters and decouple complex thermodynamic relationships within the high-dimensional design space. Furthermore, the Non-Dominated Sorting Whale Optimization Algorithm (NSWOA) is applied to construct a Pareto-optimal decision space, providing optimal strategies for waste heat recovery. This study demonstrates the efficacy of this approach in visualizing intricate system dynamics, uncovering pivotal parameters, and achieving preferable system performance. These findings underscore the potential of the proposed hybrid approach to enhance the flexibility, efficiency, and sustainability of nuclear residual heat multi-generation systems.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"189 ","pages":"Article 105946"},"PeriodicalIF":3.2,"publicationDate":"2025-07-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144738018","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}

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Modification of the turbulent model for flow in bare rod bundle based on data assimilation technology 基于数据同化技术的裸杆束湍流模型修正

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-07-30 DOI: 10.1016/j.pnucene.2025.105955

Zhenyang Sun , Hongyang Wei , Yiwei Wang , Sichao Tan , Yitung Chen

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Expanded transfer functions – A method to correlate multigroup macroscopic cross sections to non-local operational parameters 扩展传递函数。将多群宏观截面与非局部操作参数相关联的方法

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-07-30 DOI: 10.1016/j.pnucene.2025.105914

Bailey Painter, Dan Kotlyar

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Optimized fuel cycle and burnup analysis for pebble-bed reactors 球床堆燃料循环优化及燃耗分析

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-07-29 DOI: 10.1016/j.pnucene.2025.105937

Sefa Bektaş , Volkan Seker , Üner Çolak , Thomas Downar

{"title":"Optimized fuel cycle and burnup analysis for pebble-bed reactors","authors":"Sefa Bektaş , Volkan Seker , Üner Çolak , Thomas Downar","doi":"10.1016/j.pnucene.2025.105937","DOIUrl":"10.1016/j.pnucene.2025.105937","url":null,"abstract":"<div><div>In a pebble-bed reactor (PBR) core, hundreds of thousands of densely packed fuel pebbles flow slowly downward. This complicates fuel movement and extends computational time for fuel cycle analysis. To overcome this problem, a quasi-static pebble flow is combined with batch-wise refueling. Achieving an equilibrium core state requires a burnup sensitivity analysis to assess how methods for coupling neutronics with depletion impact the accuracy of burnup calculations. Numerical burnup calculations face a fundamental challenge of nonlinearity: the burnup matrix, which determines fuel depletion, varies over time due to its dependence on the neutron flux, which itself is influenced by the evolving nuclide density distributions. While the explicit Euler method is commonly used for coupling neutronics with fuel depletion, its low accuracy can be problematic in PBR applications. In contrast, the predictor–corrector method enhances accuracy but requires twice as many transport calculations, increasing computational demands. To address these challenges, this study performed a time-step optimization using the SERPENT Monte Carlo code on the HTR200 design under the once-through-then-out (OTTO) scheme. The study highlighted significant runtime reductions, from approximately 10 h to about 4 h, while analyzing the effective multiplication factor (k-eff) and key isotopes, such as Xe-135, U-235, and Pu-239.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"189 ","pages":"Article 105937"},"PeriodicalIF":3.2,"publicationDate":"2025-07-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144721037","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}

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Interpretable machine learning for quantitative parameter importance and operational thresholds in PWR accident prediction 压水堆事故预测中定量参数重要性和运行阈值的可解释机器学习

IF 3.2 3区工程技术

Progress in Nuclear Energy Pub Date : 2025-07-29 DOI: 10.1016/j.pnucene.2025.105948

Jinqi Zheng, Yichun Wu, Qing Liang, Jiale Ling, Jiayan Fang

{"title":"Interpretable machine learning for quantitative parameter importance and operational thresholds in PWR accident prediction","authors":"Jinqi Zheng, Yichun Wu, Qing Liang, Jiale Ling, Jiayan Fang","doi":"10.1016/j.pnucene.2025.105948","DOIUrl":"10.1016/j.pnucene.2025.105948","url":null,"abstract":"<div><div>The \"black box\" nature of machine learning models hinders trust and transparency in nuclear safety systems, where interpretability is critical. This study introduces an explainable CatBoost-SHAP framework for accident prediction in pressurized water reactors (PWRs). Leveraging CPR1000 reactor simulator and Optuna-optimized CatBoost, the model achieved high accuracy (R<sup>2</sup> > 0.999, MAPE <1 %) on small break loss-of-coolant accident (SBLOCA) datasets for both hot-leg and cold-leg scenario, outperforming XGBoost and LightGBM. SHAP analysis identified key thermal-hydraulic drivers (e.g., steam generator (SG) pressure <6.74 MPa, wide-range downcomer level <−1.4 %) and uncovered nonlinear interactions among multi-loop variables, consistent with reactor physics. The framework's dual capability - high predictive precision and mechanistic interpretability - enables operators to validate decision pathways and prioritize safety thresholds. By bridging the gap between opaque AI and nuclear safety demands, this work provides practical guidelines for real-time diagnostics and proactive accident mitigation in PWRs.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"189 ","pages":"Article 105948"},"PeriodicalIF":3.2,"publicationDate":"2025-07-29","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"144721035","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