期刊文献+
共找到15篇文章
< 1 >
每页显示 20 50 100
Adaptive output-feedback power-level control for modular high temperature gas-cooled reactors
1
作者 董哲 《Chinese Journal of Chemical Engineering》 SCIE EI CAS CSCD 2015年第12期2092-2097,共6页
Small modular reactors(SMRs) are beneficial in providing electricity power safely and viable for specific applications such as seawater desalination and heat production. Due to its inherent safety feature, the modular... Small modular reactors(SMRs) are beneficial in providing electricity power safely and viable for specific applications such as seawater desalination and heat production. Due to its inherent safety feature, the modular high temperature gas-cooled reactor(MHTGR) is considered as one of the best candidates for SMR-based nuclear power plants. Since its dynamics presents high nonlinearity and parameter uncertainty, it is necessary to develop adaptive power-level control, which is beneficial to safe, stable, and efficient operation of MHTGR and is easy to be implemented. In this paper, based on the physically-based control design approach, an adaptive outputfeedback power-level control is proposed for MHTGRs. This control can guarantee globally bounded closedloop stability and has a simple form. Numerical simulation results show the correctness of the theoretical analysis and satisfactory regulation performance of this control. 展开更多
关键词 high temperature gas-cooled reactor Power-level regulation Adaptive control
下载PDF
Safety Features of Modular High Temperature Gas-cooled Reactors (MHTGR) 被引量:1
2
作者 吴宗鑫 《Tsinghua Science and Technology》 SCIE EI CAS 1996年第1期8-11,共4页
The following design features which satisfy fundamental safety design objectives of an MHTGR are analyzed: (i) inherent safety features to reactivity effect: (ii) passive decay heat removal: and (iii) multiple barrier... The following design features which satisfy fundamental safety design objectives of an MHTGR are analyzed: (i) inherent safety features to reactivity effect: (ii) passive decay heat removal: and (iii) multiple barriers.Several events have been identified to be the bounding. hypothetical accidents for the MHTGR. The important accident sequences leading to severe accidents are ingress of a large amount of water or air into the core. The analyses of severe accident scenarios have shown that even the harm of fuel element predicted to occur by chmeical reaction after a hypothetical large amount of water ingress into the core or air ingress into the core will not result in major impact on the environment due to the nitegrity of fuel particles remained. Therefore, it would not be necessary to require an emergency plan to evacuate nearby inhabitants. 展开更多
关键词 modular high temperature gas-cooled reactors reactor safaty inherent safety
原文传递
超高温高功率密度的小型气冷堆堆芯方案研究
3
作者 俞荣君 杨睿 +2 位作者 李维汉 孙征 赵守智 《节能技术》 CAS 2024年第5期425-429,共5页
高温气冷堆作为小型反应堆的技术路线之一,具有模块化设计、固有安全性、热转换效率高等优势,但其功率密度较小、堆芯尺寸较大,不利于系统部署。为此,本文基于改进包覆燃料颗粒的棱柱式弥散燃料元件,并采用控制鼓作为反应性控制方式,提... 高温气冷堆作为小型反应堆的技术路线之一,具有模块化设计、固有安全性、热转换效率高等优势,但其功率密度较小、堆芯尺寸较大,不利于系统部署。为此,本文基于改进包覆燃料颗粒的棱柱式弥散燃料元件,并采用控制鼓作为反应性控制方式,提出了一种超高温、高功率密度的小型气冷堆堆芯方案。该堆芯方案体积小于0.8 m 3、体积功率密度可达39 MW/m 3,出口温度高于1200 K。通过RMC程序、Fluent软件分别进行中子学分析和热工分析,数值结果表明该方案合理可行,且具有固有安全性、具备正常停运的功能,同时拥有在15 MW热功率基础上进一步提高运行功率的能力。 展开更多
关键词 核能 小堆 气冷堆 超高温 包覆燃料颗粒 棱柱式燃料元件
下载PDF
棱柱式高温气冷堆乏燃料贮存方案研究
4
作者 李修园 王晨 《一重技术》 2024年第2期18-21,共4页
介绍棱柱式高温气冷堆乏燃料贮存工艺方案,分析棱柱式乏燃料石墨组件特点,提出适于该类型乏燃料组件的贮存方案,为核能技术可持续发展提供支持。
关键词 棱柱式高温气冷堆 乏燃料贮存 乏燃料石墨组件
下载PDF
棱柱状高温堆堆芯高效热工计算模型开发及验证
5
作者 郭娟娟 童朴 +3 位作者 孔德泰 何昉 黄善仿 王侃 《核科学与工程》 CAS CSCD 北大核心 2022年第4期792-800,共9页
棱柱状高温堆作为四代堆候选堆型之一,固有安全性高,堆芯稳定性好。该堆堆芯热工计算通常采用CFD方法,网格量大,计算效率低,且多孔介质法不适用于棱柱式高温堆堆芯的计算分析。因此,本文提出了“一维流体、三维固体”的简化热工模型,基... 棱柱状高温堆作为四代堆候选堆型之一,固有安全性高,堆芯稳定性好。该堆堆芯热工计算通常采用CFD方法,网格量大,计算效率低,且多孔介质法不适用于棱柱式高温堆堆芯的计算分析。因此,本文提出了“一维流体、三维固体”的简化热工模型,基于Multi-physics Object-Oriented Simulation Environment (MOOSE)平台开发了PHEASANT程序。分别计算了棱柱状高温堆MHTGR-350MW基准题的单通道及组件级别算例,并与CFD程序OpenFOAM的计算结果进行了对比验证,温度平均偏差为1%,最大偏差不超过3%,且PHEASANT计算时间减少90%。因此,所提出的简化热工模型准确可信,且计算效率高。 展开更多
关键词 棱柱状高温堆 堆芯热工计算 MOOSE PHEASANT OPENFOAM
下载PDF
Research on graphite powders used for HTR-PM fuel elements
6
作者 ZHAO Hongsheng LIANG Tongxiang ZHANG Jie LI Ziqiang TANG Chunhe 《Rare Metals》 SCIE EI CAS CSCD 2006年第z1期347-350,共4页
Different batches of natural graphite powders and electrographite powders were characterized by impurity, degree of graphitization, particle size distribution, specific surface area, and shape characteristics. The gra... Different batches of natural graphite powders and electrographite powders were characterized by impurity, degree of graphitization, particle size distribution, specific surface area, and shape characteristics. The graphite balls consist of proper mix-ratio of natural graphite, electrographite and phenolic resin were manufactured and characterized by thermal conductivity, anisotropy of thermal expansion, crush strength, and drop strength. Results show that some types of graphite powders possess very high purity, degree of graphitization, and sound size distribution and apparent density, which can serve for matrix graphite of HTR-PM. The graphite balls manufactured with reasonable mix-ratio of graphite powders and process method show very good properties. It is indicated that the properties of graphite balls can meet the design criterion of HTR-PM. We can provide a powerful candidate material for the future manufacture of HTR-PM fuel elements. 展开更多
关键词 high temperature gas-cooled reactor graphite powder design criterion
下载PDF
PD Power-Level Control Design for MHTGRs
7
作者 Zhe Dong 《Journal of Power and Energy Engineering》 2014年第4期130-138,共9页
Due to its inherent safety feature, the modular high temperature gas-cooled reactor (MHTGR) has been seen as one of the best candidates in building next generation nuclear plants (NGNPs). Since the MHTGR dynamics has ... Due to its inherent safety feature, the modular high temperature gas-cooled reactor (MHTGR) has been seen as one of the best candidates in building next generation nuclear plants (NGNPs). Since the MHTGR dynamics has high nonlinearity, it is necessary to develop nonlinear power-level controller which is not only beneficial to the safe, stable, efficient and autonomous operation of the MHTGR but also easy to be implemented practically. In this paper, based on the concept of shiftedectropy and the physically-based control design approach, it is proved theoretically that the simple proportional-differential (PD) output-feedback power-level control can provide globally asymptotic closed-loop stability. Numerical simulation results verify the theoretical results and show the influence of the controller parameters to the dynamic response. 展开更多
关键词 MODULAR high temperature gas-cooled reactor (MHTGR) Power-Level Control CLOSED-LOOP Stability
下载PDF
棱柱式高温气冷堆堆芯间隙旁流模拟研究
8
作者 董建华 汪俊 +1 位作者 郭娟娟 张朔婷 《核技术》 CAS CSCD 北大核心 2021年第12期76-84,共9页
棱柱式高温气冷堆的堆芯由燃料组件砖块分层、分区垒砌组成,考虑到加工误差以及结构装配,组件之间需要保证一定尺寸的间隙,形成的间隙流道将分流一部分堆芯冷却剂流量,简称间隙旁流。间隙旁流是堆芯结构以及堆内构件设计需要分析的重要... 棱柱式高温气冷堆的堆芯由燃料组件砖块分层、分区垒砌组成,考虑到加工误差以及结构装配,组件之间需要保证一定尺寸的间隙,形成的间隙流道将分流一部分堆芯冷却剂流量,简称间隙旁流。间隙旁流是堆芯结构以及堆内构件设计需要分析的重要因素,为了研究其对于反应堆热工流体性能的影响,采用商用计算流体力学(Computational Fluid Dynamics,CFD)程序ANSYS CFX针对MHTGR-350(Modular High-Temperature Gas Reactor 350 MWt)堆型堆芯活性区内流动、传热的复杂现象开展三维数值模拟,通过建立组件砖块、燃料孔道、冷却剂通道以及间隙流道的详细模型,计算得到区域内的流量分配以及温度分布情况。选取关键参数开展敏感性分析,结果显示:进入狭长间隙流道的冷却剂流量主要由堆芯的结构布置以及间隙的尺寸大小决定,间隙越大、旁流占比越大,冷却效率越差,燃料的局部温度越高。同时,在反应堆运行寿期内,间隙尺寸将随着组件形变而发生变化,引起堆内温度分布以及出口温度发生波动,间隙越大引起的波动幅度也越大,不利于堆芯运行的安全性和稳定性。 展开更多
关键词 棱柱式高温气冷堆 间隙旁流 MHTGR-350 数值模拟
下载PDF
基于VHTRC的棱柱式高温气冷堆核设计程序验证
9
作者 袁媛 张成龙 +4 位作者 刘国明 堵树宏 霍小东 冯致远 杜夏楠 《强激光与粒子束》 CAS CSCD 北大核心 2022年第2期151-156,共6页
高温气冷堆是国际公认的固有安全性高的反应堆堆型。针对高温气冷堆包覆颗粒燃料引入的燃料组件的双重非均匀性以及棱柱式堆芯布置的非均匀性和强空间耦合效应,提出基于蒙特卡罗均匀化-确定论输运方法的RMC-SaraGR程序系统作为棱柱式高... 高温气冷堆是国际公认的固有安全性高的反应堆堆型。针对高温气冷堆包覆颗粒燃料引入的燃料组件的双重非均匀性以及棱柱式堆芯布置的非均匀性和强空间耦合效应,提出基于蒙特卡罗均匀化-确定论输运方法的RMC-SaraGR程序系统作为棱柱式高温气冷堆的核设计程序。基于日本棱柱式高温气冷堆临界实验装置VHTRC基准题,针对此套核设计程序系统开展了均匀化模型研究和初步验证。研究结果表明,基于蒙特卡罗均匀化方法,采用全堆模型、合适的能群结构和分区方式产生组件群常数,并经过超级等效均匀化方法进行等效均匀化修正,可以保证堆芯多群均匀计算具有较高的计算精度。 展开更多
关键词 棱柱式高温气冷堆 蒙特卡罗均匀化 超级均匀化 全堆均匀化 堆芯输运
下载PDF
The Module HTGR Development in China
10
作者 Wu Zongxin(Institute of Nuclear and New Energy TechnologyTsinghua University,Beijing 100084,P.R.China) 《工程科学(英文版)》 2007年第4期59-67,共9页
High Temperature Gas-cooled Reactors are recognized as a representative advanced nuclear system for the future owing to the excellent safety performance,high efficiency,multipurpose uses and hydrogen production.These ... High Temperature Gas-cooled Reactors are recognized as a representative advanced nuclear system for the future owing to the excellent safety performance,high efficiency,multipurpose uses and hydrogen production.These type reactors are characterized by ceramic coated particle fuel,inert helium as coolant,and graphite used as moderator and reflector in core,which makes the outlet temperature of coolant reaching 950℃ even more.Under the National High Technology Program,the HTR-10 project has been successfully implemented and achieved full power operation in connection with the grid in January of 2003.HTR-10,which is the first module HTR with inherent safety feature around world,has carried out safety demonstration tests simulating the severe accident conditions in 2004.Based on the proven technologies and experience feedback during HTR-10 design,manufacture,construction and operation,a HTR-PM demonstration power plant with 200MWe power capacity sited at Rongcheng of Shandong province has been initiated. 展开更多
关键词 MODULE high temperature gas-cooled reactor PASSIVE DECAY heat REMOVAL inherent safety
下载PDF
Experimental and mechanistic study of dispersed micrometer-sized particle resuspension in a square straight duct with rough walls
11
作者 Qi Sun Suyuan Yu Wei Peng 《Particuology》 SCIE EI CSCD 2023年第12期101-114,共14页
The resuspension of graphite dust is an important phenomenon in the release of radioactivity and the safety of nuclear reactors during severe accidents.In this study,a visualization experimental platform is constructe... The resuspension of graphite dust is an important phenomenon in the release of radioactivity and the safety of nuclear reactors during severe accidents.In this study,a visualization experimental platform is constructed to study effects of particle size,flow velocity,and wall roughness on the resuspension characteristics of graphite particles.A statistical model of particle resuspension applicable to monolayer dispersed particles is developed based on the moment equilibrium of the particles and the flow field characteristics,as calculated by the large-eddy simulation framework.The results show that particle resuspension can be divided into short-and long-term resuspension stages.Most particle resuspension occurs during the short-term stage.With increases in flow velocity and particle diameter,the aerodynamic or adhesion force acting on the particles increases,and corresponding particle resuspension fraction increases.The influence of rough walls on particle resuspension is related to both the force on the particles and the arm ratio between the wall morphology and the particle diameter.A comparison with the experimental results demonstrates that the particle resuspension model developed in this study accurately predicts the impact of flow velocity,particle size,and wall roughness on particle resuspension. 展开更多
关键词 Particle resuspension Statistical model Moment equilibrium high temperature gas-cooled reactor(HTGR)
原文传递
Research on the Silicon Carbide Layer of Coated Fuel Particles
12
作者 徐世江 杨冰 +3 位作者 朱钧国 张秉忠 张冬梅 张纯 《Tsinghua Science and Technology》 SCIE EI CAS 1996年第1期45-49,共5页
The 10MW high temperature gas-cooled test reactor (HTR-10) under construction at INET uses whole ceramic fuel elements. The main barrier which prevents fission product release is the SiC layer of the coated fuel parti... The 10MW high temperature gas-cooled test reactor (HTR-10) under construction at INET uses whole ceramic fuel elements. The main barrier which prevents fission product release is the SiC layer of the coated fuel particles. Fabrication of high quality SiC layers is one of the key R&D tasks for the HTR-10 fuel element. The SiClayer was deposited on the fuel particles in a 50 mm conical fluidized bed using the CVD (chemical vapour deposition) technique. The density, thickness, strength and elastic modulus of the SiC layer were measured. The microstructure was observed using SEM (scanning electron microscope ). Parameters were established for manufacturing the SiC layer of the coated fuel particles to be used in the HTR-10. It was found that the traditional density measurement by the sink-float method is questionable in the low density region and that the SiC layer may be contaminated by uranium under certain conditions. 展开更多
关键词 high temperature gas-cooled reactor fuel element coated fuel particle SIC DENSITY STRENGTH MICROSTRUCTURE uranium contamination
原文传递
Thermochemical Water Splitting for Hydrogen Production Utilizing Nuclear Heat from an HTGR
13
作者 吴莘馨 ONUKI Kaoru 《Tsinghua Science and Technology》 SCIE EI CAS 2005年第2期270-276,共7页
A very promising technology to achieve a carbon free energy system is to produce hydrogen from water, rather than from fossil fuels. Iodine-sulfur (IS) thermochemical water decomposition is one promising process. Th... A very promising technology to achieve a carbon free energy system is to produce hydrogen from water, rather than from fossil fuels. Iodine-sulfur (IS) thermochemical water decomposition is one promising process. The IS process can be used to efficiently produce hydrogen using the high temperature gas-cooled reactor (HTGR) as the energy source supplying gas at 1000℃. This paper describes that dem- onstration experiment for hydrogen production was carried out by an IS process at a laboratory scale. The results confirmed the feasibility of the closed-loop operation for recycling all the reactants besides the water, H2, and O2. Then the membrane technology was developed to enhance the decomposition efficiency. The maximum attainable one-pass conversion rate of HI exceeds 90% by membrane technology, whereas the equilibrium rate is about 20%. 展开更多
关键词 high temperature gas-cooled reactor hydrogen production THERMOCHEMICAL water splitting
原文传递
Oxidation Behaviour of the Matrix Materials in Spherical Fuel Elements
14
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)
原文传递
Feasibility of Burning Civilian Grade Pu in the Modular HTR with Th Fuel Cycle
15
作者 许云林 经荥清 《Tsinghua Science and Technology》 SCIE EI CAS 2001年第1期80-83,共4页
The Modular High Temperature Gas-Cooled Reactor (HTR) can be used to burn plutonium fuel to reduce Pu stockpiles because of its inherent safety characteristics and ability to burn a variety of fuel mixtures. The equil... The Modular High Temperature Gas-Cooled Reactor (HTR) can be used to burn plutonium fuel to reduce Pu stockpiles because of its inherent safety characteristics and ability to burn a variety of fuel mixtures. The equilibrium core is calculated and analyzed for Pu enriched fuel. Fuel spheres with 7g heavy metal including the civilian grade Pu and thorium are loaded into the reactor. An enrichment of 11% is chosen to provide the desired equilibrium core reactivity. The fuel and moderator temperature coefficients are both negative. The maximum fuel element temperature during normal operation and during a loss of coolant accident is less than 1500℃. 92% of 239 Pu will be burnt during nomal operation. Therefore, a thorium fuel cycle in the modular HTR is an effective method for burning civilian grade plutonium. 展开更多
关键词 burning plutonium Th fuel cycle Modular high temperature gas-cooled reactor (HTR)
原文传递
上一页 1 下一页 到第
使用帮助 返回顶部