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Densification and thermal properties of cylindrical graphite-based fuel elements used in a molten salt reactor
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作者 WANG Gan WANG Hao-ran +5 位作者 LU Lin-yuan LI Wan-lin CHEN Nan-nan HE Yun ZHONG Ya-juan LIN Jun 《新型炭材料(中英文)》 北大核心 2025年第6期1362-1376,I0059,共16页
Based on the service characteristics of fuel elements for molten salt reactors,they need to have a high power density,resistance to coolant infiltration,and excellent thermodynamic properties.To solve the problem of t... Based on the service characteristics of fuel elements for molten salt reactors,they need to have a high power density,resistance to coolant infiltration,and excellent thermodynamic properties.To solve the problem of the graphite used in the fuel element for these reactors being susceptible to molten salt infiltration,carbon black(CB)was added to increase the density of the graphite,and a fuel element(TRISO(tri-structural isotropic)fuel particles were randomly distributed in the modified graphite matrix)was prepared by cold isostatic pressing process.An out-of-pile performance study shows that the densification and pore structure of the modified graphite matrix were improved,as was the resistance to molten salt infiltration.The median pore size of the modified graphite was reduced from 673 to 433 nm and the threshold pressure for molten salt(FLiBe,66%(molar fraction)LiF and 34%BeF_(2))infiltration was increased from 0.88 to 1.37 MPa.The isotropic CB made the graphite matrix less anisotropic,while its thermal conductivity and compressive strength were reduced due to the difficult graphitization of CB.Fuel elements containing 20%(volume fraction)TRISO particles were prepared.Numerical simulations show that the power and temperature distribution of the fuel were in line with the design requirements.The modified graphite matrix had a higher density,smaller pores,a lower anisotropy and a greater resistance to FLiBe infiltration. 展开更多
关键词 Molten salt reactor Cylindrical fuel element Graphite matrix Thermal properties Molten salt infiltration
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Topology optimization of fuel elements for additive manufacturing to enhance the fluid-thermal performance of nuclear fuel assemblies
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作者 Dong Huo Yile Zhang +5 位作者 Ying Zhou Liang Meng Yong Xin Taiying Liu Jihong Zhu Weihong Zhang 《Additive Manufacturing Frontiers》 2025年第4期63-72,共10页
The integration of additive manufacturing(AM)and topology optimization(TO)has revolutionized the design and production of advanced equipment,providing innovative approaches to solving complex engineering challenges.In... The integration of additive manufacturing(AM)and topology optimization(TO)has revolutionized the design and production of advanced equipment,providing innovative approaches to solving complex engineering challenges.In the nuclear energy sector,achieving an optimal balance between the thermal and hydraulic performance of prismatic fuel elements has long been a key challenge.This study utilizes a coupled fluid-thermal TO method to design fuel elements with one,three,five,and seven inlets/outlets configurations suitable for AM.We systematically examine the impact of varying the number of inlets/outlets on the thermal-hydraulic performance of the elements.The results show that increasing the number of inlets/outlets can enhance the thermal performance of the fuel elements while sacrificing the hydraulic performance.Compared with the conventional design,the 5 inlets/outlets configuration achieved a coordinated improvement in both thermal and hydraulic performance,with a 2.38%enhancement in thermal performance and a 4.38%improvement in hydraulic performance.These findings highlight the significant potential of TO in improving the performance of fuel elements and strongly demonstrate the advantages of the collaborative application of AM and TO. 展开更多
关键词 Topology optimization Additive manufacturing fuel elements Thermal-hydraulic coupling Nuclear industry
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Research on manufacture technology of spherical fuel elements by dry-bag isostatic pressing 被引量:1
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作者 Zhen-Ming Lu Wen-Ke Zhang +5 位作者 Jie Zhang Xiang-Wen Zhou Kai-Hong Zhang Ma-Lin Liu Xuan-Ke Li Bing Liu 《Nuclear Science and Techniques》 SCIE EI CAS CSCD 2022年第10期79-89,共11页
The steady development of high-temperature gas-cooled reactors(HTRs) has increased the requirements for the production cost and quality of fuel elements. Green fuel element pressing is one of the key steps to increase... The steady development of high-temperature gas-cooled reactors(HTRs) has increased the requirements for the production cost and quality of fuel elements. Green fuel element pressing is one of the key steps to increase the production capacity. This paper proposes a proprietary vacuum dry-bag isostatic pressing(DIP) apparatus. The structural change of the matrix graphite powder during the DIP process was examined by analyzing the density change of the matrix graphite spheres with pressure. The soft molding process was simulated using the finite element method. The dimensional changes in the spheres during the pressing, carbonization, and purification stages were explored. The performance of the fuel matrix produced by the DIP method was comprehensively examined. The fuel matrix met the technical requirements and its anisotropy was significantly reduced. The DIP method can significantly improve both the production efficiency and quality of fuel elements. This will play a key role in meeting the huge demand for fuel elements of HTRs and molten salt reactors. 展开更多
关键词 Dry-bag isostatic pressing High-temperature gas-cooled reactor(HTR) Spherical fuel element Finite element simulation Soft molding
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Manufacture of HTR Fuel Element
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作者 Shijiang, X. Chunhe, T. +3 位作者 Zhichang, X. Junguo, Zh. Xueliang, Q. Ende, L. 《High Technology Letters》 EI CAS 1995年第1期87-90,共4页
The HTR Fuel Element R & D Program,set in 1987,aims to develop the manufacturetechnology of HTR fuel element and to produce the fuel element for the first core of our 10MW experimental reactor.Now the work on labo... The HTR Fuel Element R & D Program,set in 1987,aims to develop the manufacturetechnology of HTR fuel element and to produce the fuel element for the first core of our 10MW experimental reactor.Now the work on laboratory scale is phased out.In this paper,the fuel element manufacture technology is described and the test results are given. 展开更多
关键词 High temperature reactor Coated fuel particles Spherical fuel element Irradiation qualification
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A method for 3D simulation of internal gas effects on thermal-mechanical behaviors in nuclear fuel elements
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作者 JIANG Yijie CUI Yi HUO Yongzhong DING Shurong 《Nuclear Science and Techniques》 SCIE CAS CSCD 2011年第3期185-192,共8页
A new method for three-dimensional simulation of the interaction between the gas and the solid around is developed.The effects of the gas on the thermal-mechanical behaviors within the surrounded solid are performed b... A new method for three-dimensional simulation of the interaction between the gas and the solid around is developed.The effects of the gas on the thermal-mechanical behaviors within the surrounded solid are performed by replacing the internal gas with an equivalent solid in the modeling,which can make it convenient to simulate the thermal-mechanical coupling effects in the solid research objects with gases in them.The applied thermal expansion coefficient,Young's modulus and Poisson's ratio of the equivalent solid material are derived.A series of tests have been conducted;and the proposed equivalent solid method to simulate the gas effects is validated. 展开更多
关键词 热机械行为 气体效应 三维模拟 核燃料元件 仿真方法 热膨胀系数 相互作用 耦合效应
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Modeling of Fuel Elements Cycling System in Pebble Bed Reactor Based on Timed Places Control Petri Nets
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作者 Hongbing Liu Peng Shen +2 位作者 Dong Du Xin Wang Haiquan Zhang 《Energy and Power Engineering》 2013年第4期510-516,共7页
Pebble bed reactors use cycling scheme of spherical fuel elements relying on fuel elements cycling system (FECS). The structure and control logic of FECS are very complex. Each control link has strict requirements on ... Pebble bed reactors use cycling scheme of spherical fuel elements relying on fuel elements cycling system (FECS). The structure and control logic of FECS are very complex. Each control link has strict requirements on time and sequence. This increases the difficulties of description and analysis. In this paper, timed places control Petri nets (TPCPN) is applied for the modeling of FECS. On this basis the simulation of two important processes, namely uploading fuel elements into the core for the first time and emptying the core is finished by simulation software Arena. The results show that as TPCPN is able to describe different kinds of logic relationship and has time properties and control properties, it’s very suitable for the modeling and analysis of FECS. 展开更多
关键词 TIMED PLACES CONTROL Petri nets (TPCPN) Arena PEBBLE Bed Reactors fuel elements CYCLING SYSTEM (FECS)
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Oxidation Behaviour of the Matrix Materials in Spherical Fuel Elements
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作者 张世超 贺俊 +1 位作者 邱学良 马昌文 《Tsinghua Science and Technology》 SCIE EI CAS 1996年第1期50-55,共6页
The oxidation resistance of the matrix materials is vital to the normal operation of HTGR and is also an important parameter for evaluating the safety response under accidental air or water ingress conditions. The oxi... The oxidation resistance of the matrix materials is vital to the normal operation of HTGR and is also an important parameter for evaluating the safety response under accidental air or water ingress conditions. The oxidation kinetics of the three matrix material components: natural graphite, artificial graphite and resin carbon. was studied in a flowing gas mixture of oxygen and nitrogen using an auto thermogravimetric system. The results indicate that the artificial graphite has the slowest oxidation rate followed by the natural graphite and then the resin carbon with the highest oxidation rate. Vacuum heat treatment of the natural graphite at 1950℃ decreases the impurities and increases the oxidation activation energy. Differences between the activation energy and the oxidation rate of the resin carbon heat treated at 1950℃ and 1600℃ resulted from changes in the micro-pore texture. and the reduction of impurities. 展开更多
关键词 OXIDATION matrix materials fuel element GRAPHITE high temperature gas-cooled reactor (HTGR)
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熔盐堆应急排盐冷却系统换热管内层屏障破损传热影响
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作者 孙亮洁 梁荣健 +4 位作者 蒋文涛 王超群 杨群 何兆忠 邹杨 《核技术》 北大核心 2026年第2期154-165,共12页
液体燃料熔盐堆是第四代先进核能系统的候选堆型之一,应急排盐冷却系统是其可设置的特殊安全设计。本文以熔盐实验堆(Molten Salt Reactor Experiment,MSRE)应急排盐冷却系统为研究对象,探究换热元件内层屏障破损对其正常余热导出功能... 液体燃料熔盐堆是第四代先进核能系统的候选堆型之一,应急排盐冷却系统是其可设置的特殊安全设计。本文以熔盐实验堆(Molten Salt Reactor Experiment,MSRE)应急排盐冷却系统为研究对象,探究换热元件内层屏障破损对其正常余热导出功能的影响。该研究基于计算流体动力学(Computational Fluid Dynamics,CFD)模拟方法,通过构建传热和多相流动模型分析破损后的传热和流动现象,并对关键影响参数进行敏感性分析。结果表明,内层套管破损后,18.4%的冷却水从破损位置经气隙层流出,单根换热元件功率提升到29.434 kW,破损位置附近外层套管出现局部温度低点。敏感性分析结果表明,破损尺寸、破损位置和气隙层压力变化均会对换热元件传热产生明显影响,其中传热对破损尺寸的敏感性最强。该分析结果可以为熔盐堆应急排盐冷却系统工程设计提供研究数据。 展开更多
关键词 熔盐堆 应急排盐冷却系统 换热元件 冷却介质泄漏 计算流体动力学
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电控喷油嘴高压油道的密封性能
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作者 韩宗祺 孔晨 +4 位作者 崔毅 龚田泓 杨博耀 张永琦 刘硕 《内燃机工程》 北大核心 2026年第1期187-194,共8页
建立喷油器体–导向体接触密封静力学计算模型,采用Whalen简化方法评价密封性能,采用Archard模型描述磨损过程,开展密封表面形貌特征及接触面微动磨损对喷油器体–导向体平面密封性能的影响机理和规律研究。结果表明:随着密封凸台相对... 建立喷油器体–导向体接触密封静力学计算模型,采用Whalen简化方法评价密封性能,采用Archard模型描述磨损过程,开展密封表面形貌特征及接触面微动磨损对喷油器体–导向体平面密封性能的影响机理和规律研究。结果表明:随着密封凸台相对于支撑凸台增高,喷油器密封性能变好;随着密封面平面度增大,喷油器密封性能变差;密封接触面微动磨损在喷油器工作初始阶段可以提高密封性能,之后持续降低密封性能。 展开更多
关键词 喷油器 密封性能 平面度 磨损 有限元
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U_(3)Si_(2)-Al弥散燃料等效热导率数值计算及建模方法研究
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作者 李勇 李强 +2 位作者 曹志伟 徐苗苗 赵晓晗 《核技术》 北大核心 2026年第2期145-153,共9页
U_(3)Si_(2)-Al弥散燃料因其高铀密度和优异的热性能,被广泛应用于研究试验堆。为准确计算其等效热导率,需考虑该燃料的微观结构特征,采用ABAQUS软件,结合自动化建模脚本,实现了多面体形状U_(3)Si_(2)颗粒在Al基体中随机分布的有限元模... U_(3)Si_(2)-Al弥散燃料因其高铀密度和优异的热性能,被广泛应用于研究试验堆。为准确计算其等效热导率,需考虑该燃料的微观结构特征,采用ABAQUS软件,结合自动化建模脚本,实现了多面体形状U_(3)Si_(2)颗粒在Al基体中随机分布的有限元模型构建及传热计算,并研究了不同简化建模方法对等效热导率计算结果的影响。研究结果表明:U_(3)Si_(2)颗粒体积分数为20%~35%、温度范围300~673 K,有限元计算的等效热导率与Maxwell-Eucken模型吻合较好;二维有限元模型计算结果比三维模型计算结果相对偏小约16%;颗粒体积因子大于0.66时,将U_(3)Si_(2)颗粒简化为球形和规则分布方式,等效热导率计算结果相对偏差小于2.1%。对U_(3)Si_(2)颗粒形状和分布方式进行简化,可以提高建模计算效率,并保证U_(3)Si_(2)-Al弥散燃料等效热导率计算结果的准确性。 展开更多
关键词 U_(3)Si_(2)-Al弥散燃料 等效热导率 有限元方法 燃料颗粒形状和分布
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包钢4000 m^(3)级高炉大比例配加湿熄焦生产实践
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作者 高靖文 曲玉云 +3 位作者 刘耀 石钢 魏国良 张敏强 《包钢科技》 2026年第1期26-30,共5页
包钢大型高炉大比例配加湿熄焦后,高炉炉况出现波动,产量降低16.26%,焦比升高7.23%。通过分析焦炭质量变化、烧结矿冶金性能、入炉有害元素负荷及对应的炉况变化,为下一步大型高炉大比例配加湿熄焦冶炼提供参考。
关键词 高炉 大比例湿熄焦 原燃料 有害元素
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质子交换膜燃料电池微孔层微结构力学特性分析
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作者 邵轩宇 黄治平 +2 位作者 许杰 张恒 詹志刚 《重庆大学学报》 北大核心 2026年第1期40-50,共11页
微孔层在质子交换膜燃料电池中起着水-气-热-电传输的重要作用,在机械应力作用下的变形及微结构的破坏将严重影响这种传输作用。通过实验制备微孔层并进行表征,量测其应力-应变关系;基于实验表征获得的特性参数,随机数值重构出微孔层的... 微孔层在质子交换膜燃料电池中起着水-气-热-电传输的重要作用,在机械应力作用下的变形及微结构的破坏将严重影响这种传输作用。通过实验制备微孔层并进行表征,量测其应力-应变关系;基于实验表征获得的特性参数,随机数值重构出微孔层的三维微观结构;使用有限元方法模拟其在不同机械作用下的形变,分别获得碳颗粒和聚四氟乙烯(polytetrafluoroethylene,PTFE)在不同应变下的位移-应力分布。结果表明:机械作用会使微孔层微结构产生显著应变,且位于应力施加侧表面应力和应变最大,更易产生应力集中现象;随着机械应变的增加,在受力方向上,应力会呈指数形式增大;当应变为10%时,碳颗粒和PTFE上的应力的最大值约为31.385 MPa和14.873MPa;当应变增加到40%时,应力的最大值变为160.03 MPa和96.165 MPa,此时应力集中最为明显;微孔层中应力集中区域会随着应变的增大而明显变大。 展开更多
关键词 质子交换膜燃料电池 微孔层 机械应力 有限元分析
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含锕系元素熔盐体系的分子动力学模拟进展
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作者 冯煊炜 姚本林 +2 位作者 贾艳虹 何辉 李俊乐 《化学通报(中英文)》 北大核心 2026年第2期155-164,共10页
研究锕系元素熔盐体系的理化性质,对于熔盐反应堆的设计和开发以及乏燃料的干法后处理中的锕系元素分离过程具有重要意义。分子动力学的方法模拟真实的熔盐体系,可以从理论的角度预测熔盐体系的理化性质,为后续的实验提供一定的理论依... 研究锕系元素熔盐体系的理化性质,对于熔盐反应堆的设计和开发以及乏燃料的干法后处理中的锕系元素分离过程具有重要意义。分子动力学的方法模拟真实的熔盐体系,可以从理论的角度预测熔盐体系的理化性质,为后续的实验提供一定的理论依据和指导。经典分子动力学经过过去几十年的发展,技术上趋于成熟,第一性原理分子动力学也在近十年内达到了新的高峰,它们各有优缺点,通过机器学习的连接,可以高效且精准地模拟含锕系元素的熔盐体系。通过对含锕系元素的熔盐体系理化性质模拟结果的分析,证明了分子动力学对该体系的模拟的成功,并且预测未来此方向分子动力学的研究应该是多种方法结合的模式。 展开更多
关键词 锕系元素 熔盐 分子动力学 机器学习 乏燃料后处理
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In-core fuel management strategy for the basket-fuel-assembly molten salt reactor 被引量:1
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作者 Chun Xue Zhi-Yong Zhu +1 位作者 Hai-Qing Zhang Jun Lin 《Nuclear Science and Techniques》 SCIE CAS CSCD 2017年第9期87-99,共13页
Molten salt reactor, with good economics and inherent reliability, is one of the six types of Generation IV candidate reactors. The Basket-Fuel-Assembly Molten Salt Reactor(BFAMSR) is a new concept design based on fue... Molten salt reactor, with good economics and inherent reliability, is one of the six types of Generation IV candidate reactors. The Basket-Fuel-Assembly Molten Salt Reactor(BFAMSR) is a new concept design based on fuel assemblies composed of fuel pebbles made of TRISOcoated particles. Four refueling patterns, similar to the fuel management strategy for water reactors, are designed and analyzed for BFAMSR in terms of economy and security.The MCNPX is employed to calculate the parameters, such as the total duration time, cycle length, discharge burnup,total discharge quantity of ^(235)U, total discharge quantity of ^(239)Pu, neutron flux distribution and power distribution. The in–out loading pattern has the highest burnup and duration time, the worst neutron flux and power distribution and the lowest neutron leakage. The out–in pattern possesses the most uniform neutron flux distribution, the lowest burnup and total duration time, and the highest neutron leakage.The out–in partition alternate pattern has slightly higher burnup, longer total duration time and smaller neutron leakage than that of the out–in loading pattern at the cost of sacrificing some neutron flux distribution and power distribution. However, its alternative distribution of fuelelements cut down the refueling time. The low-leakage pattern is the second highest in burnup, and total duration time, and its neutron flux and power distributions are the second most uniform. 展开更多
关键词 堆芯燃料管理 燃料组件 熔盐堆 中子通量分布 反应堆 持续时间 包覆燃料颗粒 中子泄漏
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Elliptical formation control based on relative orbit elements 被引量:3
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作者 Yin Jianfeng Han Chao 《Chinese Journal of Aeronautics》 SCIE EI CAS CSCD 2013年第6期1554-1567,共14页
A new set of relative orbit elements(ROEs)is used to derive a new elliptical formation flying model.In-plane and out-of-plane motions can be completely decoupled,which benefts elliptical formation design.The inverse... A new set of relative orbit elements(ROEs)is used to derive a new elliptical formation flying model.In-plane and out-of-plane motions can be completely decoupled,which benefts elliptical formation design.The inverse transformation of the state transition matrix is derived to study the relative orbit control strategy.Impulsive feedback control laws are developed for both in-plane and out-of-plane relative motions.Control of in-plane and out-of-plane relative motions can be completely decoupled using the ROE-based feedback control law.A tangential impulsive control method is proposed to study the relationship of fuel consumption and maneuvering positions.An optimal analytical along-track impulsive control strategy is then derived.Different typical orbit maneuvers,including formation establishment,reconfguration,long-distance maneuvers,and formation keeping,are taken as examples to demonstrate the performance of the proposed control laws.The effects of relative measurement errors are also considered to validate the high accuracy of the proposed control method. 展开更多
关键词 Elliptical formation control Formation flying fuel optimal Impulsive control Relative orbit elements
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MULTIPOINT BLANK HOLDER FORCE CONTROL IN HYDROFORMING OF FUEL TANK 被引量:4
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作者 WU Yousheng WANG Xinyun +3 位作者 XIA Juchen HU Guoan SUN Yousong YANG Lin 《Chinese Journal of Mechanical Engineering》 SCIE EI CAS CSCD 2006年第2期200-204,共5页
The study of multipoint blank holder force(BHF) control is carried out for hydroforming a complicated shape motorcycle fuel tank. By finite element method (FEM) simulation, the configuration of multipoint blank ho... The study of multipoint blank holder force(BHF) control is carried out for hydroforming a complicated shape motorcycle fuel tank. By finite element method (FEM) simulation, the configuration of multipoint blank holder cylinders and the setting of local BHF are optimized, and the influences of the multipoint BHF on the hydromechanical deep drawing and conventional hydroforming processes are studied. The desired fluid pressure and whole BHF are predicted for hydromechanical deep drawing process. Finally, simulation results are testified by forming experiment, and they are in agreement very well. 展开更多
关键词 HYDROFORMING Multipoint blank holder force (BHF) fuel tank Finite element method (FEM)
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Finding an optimization of the plate element of Egyptian research reactor using genetic algorithm
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作者 WAHED Mohamed IBRAHIM Wesam EFFAT Ahmed 《Nuclear Science and Techniques》 SCIE CAS CSCD 2008年第5期314-320,共7页
The second Egyptian research reactor ET-RR-2 went critical on the 27th of November 1997.The National Center of Nuclear Safety and Radiation Control (NCNSRC) has the responsibility of the evaluation and assessment of t... The second Egyptian research reactor ET-RR-2 went critical on the 27th of November 1997.The National Center of Nuclear Safety and Radiation Control (NCNSRC) has the responsibility of the evaluation and assessment of the safety of this reactor.The purpose of this paper is to present an approach to optimization of the fuel element plate. For an efficient search through the solution space we use a multi objective genetic algorithm which allows us to identify a set of Pareto optimal solutions providing the decision maker with the complete spectrum of optimal solutions with respect to the various targets.The aim of this paper is to propose a new approach for optimizing the fuel element plate in the reactor.The fuel element plate is designed with a view to improve reliability and lifetime and it is one of the most important elements during the shut down.In this present paper,we present a conceptual design approach for fuel element plate,in conjunction with a genetic algorithm to obtain a fuel plate that maximizes a fitness value to optimize the safety design of the fuel plate. 展开更多
关键词 埃及核反应堆 遗传算法 燃料元件 核技术
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Studies on Capacity Expansion of Fuel Plants for Nuclear Research Reactors
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作者 Miguel Luiz Miotto Negro Michelangelo Durazzo +3 位作者 Marco Aurélio de Mesquita Elita Fontenele Urano de Carvalho Roberto Navarro de Mesquita Delvonei Alves de Andrade 《World Journal of Nuclear Science and Technology》 2018年第2期38-53,共16页
The demand for nuclear fuel for research reactors is rising worldwide. Thus, the production facilities of this kind of fuel need reliable guidance on how to augment their production in order to meet the increasing dem... The demand for nuclear fuel for research reactors is rising worldwide. Thus, the production facilities of this kind of fuel need reliable guidance on how to augment their production in order to meet the increasing demand efficiently and safely. We proposed a specific procedure for increasing production capacity. That procedure was tested with data from a real plant, which produces plate-type fuel elements loaded with LEU U3Si2-Al fuel. The test was made by means of discrete event simulation, and the results indicated the proposed procedure is efficient in raising production capacity. 展开更多
关键词 Fabrication of URANIUM SILICIDE fuel PLATE-TYPE fuel elements NUCLEAR Research Reactors Production Capacity EXPANSION
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高效液相色谱-电感耦合等离子体质谱法测定核燃料中锕系元素、稳定及长半衰期裂变产物
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作者 梁帮宏 苏冬萍 +8 位作者 程宇 蔡天培 郭志谋 甘泉 罗婷 李顺涛 张劲松 陈云明 曹骐 《质谱学报》 北大核心 2025年第3期301-311,共11页
分析辐照后核燃料中的裂变产物和锕系元素对基础研究和工程应用具有重要意义。本文采用高效液相色谱-电感耦合等离子体质谱(HPLC-ICP-MS)法对核燃料中锕系元素、稳定及长半衰期裂变产物进行分析,设计了具有疏水作用和阳离子交换作用的... 分析辐照后核燃料中的裂变产物和锕系元素对基础研究和工程应用具有重要意义。本文采用高效液相色谱-电感耦合等离子体质谱(HPLC-ICP-MS)法对核燃料中锕系元素、稳定及长半衰期裂变产物进行分析,设计了具有疏水作用和阳离子交换作用的分离材料,使裂变产物和锕系元素在单根色谱柱上分离。通过控制α-羟基异丁酸(HIBA)的浓度和pH值,实现铀与镧系元素的分离。实验设计了色谱与质谱连接的流路,具备独立使用和联用的模式切换、流量控制等功能,并对辐照后核燃料样品进行分析,获得了La、Ce、Pr、Nd、Pm、Sm、Eu、Gd、Y、Rb、Mo、Zr、Cs、U、Np、Pu等元素的色谱流出曲线和部分半定量结果。该方法分析效率高、抗干扰能力强,可用于形态价态分析,以及乏燃料及辐照靶件中少量组分的提纯制备。 展开更多
关键词 高效液相色谱-电感耦合等离子体质谱(HPLC-ICP-MS) 核燃料 镧系元素 锕系元素 裂变产物
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基于D-D中子源的中子毒物材料检测技术研究
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作者 罗建东 李严星 +6 位作者 潘喆 韦峥 吴康 雷浩宇 李嘉旋 高三杰 陈洪生 《材料研究与应用》 2025年第3期531-536,共6页
随着核能技术的不断发展,燃料元件的运行寿命和安全性面临着更高的要求。通过在燃料元件芯体中添加中子毒物可以有效提升反应堆系统的安全性与稳定性,而准确检测中子毒物的含量则成为关键环节。利用中子毒物的高中子吸收截面特性,采用... 随着核能技术的不断发展,燃料元件的运行寿命和安全性面临着更高的要求。通过在燃料元件芯体中添加中子毒物可以有效提升反应堆系统的安全性与稳定性,而准确检测中子毒物的含量则成为关键环节。利用中子毒物的高中子吸收截面特性,采用模拟与实验相结合的方法,开展了基于D-D中子源的中子毒物含量无损检测方法研究,并对其可靠性进行了评估。采用Geant4蒙特卡罗模拟软件,建立燃料元件中子毒物含量与透射热中子强度的响应模型,获得毒物元素含量与中子透射率的演化规律。基于紧凑型DD中子源建立硼材料中子毒物的检测方法,设计专用的中子慢化体将2.45 MeV的快中子慢化到He-3探测器探测灵敏的热中子,通过模拟计算获得He-3探测器的效率曲线,并利用高效He-3探测器对透射热中子进行探测。通过与EJ-309液体闪烁体探测器监测的中子产额进行归一化计算得到中子透射率,进而确定实验中子透射率与中子毒物含量之间的关系。研究结果表明,不同B4C质量分数的Geant4模拟计算结果与实验结果偏差不超过3%。采用破坏性化学分析方法对检测精度进行验证,基于D-D中子源的检测方法对中子毒物含量的检测精度优于5%,验证了本技术方法的可靠性与准确性。作为一种新型的核燃料芯块中子毒物含量非破坏性分析技术,该方法可应用于燃料芯块中子毒物含量及空间均匀性在线检测,助力我国核能的安全高效发展。 展开更多
关键词 D-D中子源 中子毒物 中子慢化 热中子 He-3探测器 燃料元件 无损检测 蒙特卡罗模拟
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