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The Shandong Shidao Bay 200 MW_e High-Temperature Gas-Cooled Reactor Pebble-Bed Module(HTR-PM) Demonstration Power Plant: An Engineering and Technological Innovation 被引量:20
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作者 张作义 董玉杰 +10 位作者 李富 张征明 王海涛 黄晓津 李红 刘兵 吴莘馨 王宏 刁兴中 张海泉 王金华 《Engineering》 SCIE EI 2016年第1期119-123,共5页
In 2005, the US passed the Energy Policy Act of 2005 mandating the construction and operation of a high-temperature gas reactor (HTGR) by 2021. This law was passed after a multiyear study by national experts on what... In 2005, the US passed the Energy Policy Act of 2005 mandating the construction and operation of a high-temperature gas reactor (HTGR) by 2021. This law was passed after a multiyear study by national experts on what future nuclear technologies should be developed. As a result of the Act, the US Congress chose to develop the so-called Next-Generation Nuclear Plant, which was to be an HTGR designed to produce process heat for hydrogen production. Despite high hopes and expectations, the current status is that high temperature reactors have been relegated to completing research programs on advanced fuels, graphite and materials with no plans to build a demonstration plant as required by the US Con- gress in 2005. There are many reasons behind this diminution of HTGR development, including but not limited to insufficient government funding requirements for research, unrealistically high temperature requirements for the reactor, the delay in the need for a "hydrogen" economy, competition from light water small modular light water reactors, little utility interest in new technologies, very low natural gas prices in the US, and a challenging licensing process in the US for non-water reactors. 展开更多
关键词 high temperature gas reactor Next-Generation Nuclear Plant (NGNP) LICENSING Nuclear Regulatory CommissionEnergy Policy Act of 2005Research status
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Numerical investigations of thermal mixing performance of a hot gas mixing structure in high-temperature gas-cooled reactor 被引量:2
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作者 Yang-Ping Zhou Peng-Fei Hao +1 位作者 Xi-Wen Zhang Feng He 《Nuclear Science and Techniques》 SCIE CAS CSCD 2016年第1期149-155,共7页
A numerical simulation study was performed to clarify the thermal mixing characteristics of coolant in the core bottom structure of the high-temperature gas-cooled reactor(HTR). The flow field and temperature field in... A numerical simulation study was performed to clarify the thermal mixing characteristics of coolant in the core bottom structure of the high-temperature gas-cooled reactor(HTR). The flow field and temperature field in the hot gas chamber and the hot gas duct of the HTR were obtained based on the commercial computational fluid dynamics(CFD) program. The numerical simulation results showed that the helium flow with different temperatures in the hot gas mixing chamber and the hot gas duct mixed intensively, and the mixing rate of the temperature in the outlet of the hot gas duct reached 98 %. The results indicated many large-scale swirling flow structures and strong turbulence in the hot gas mixing chamber and the entrance of the hot gas duct, which were responsible for the excellent thermal mixing of the hot gas chamber and the hot gas duct. The calculated results showed that the temperature mixing rate of the hot gas chamber decreased only marginally with increasing Reynolds number. 展开更多
关键词 高温气冷堆 混合性能 混合结构 热气体 数值研究 计算流体动力学 数值模拟 热气导管
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Design of the material performance test apparatus for high temperature gas-cooled reactor 被引量:1
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作者 REN Cheng YANG Xing Tuan +2 位作者 LI Cong Xin LIU Zhi Yong JIANG Sheng Yao 《Nuclear Science and Techniques》 SCIE CAS CSCD 2013年第6期132-136,共5页
Most materials can be easily corroded or ineffective in carbonaceous atmospheres at high temperatures in the reactor core of the high temperature gas-cooled reactor(HTGR).To solve the problem,a material performance te... Most materials can be easily corroded or ineffective in carbonaceous atmospheres at high temperatures in the reactor core of the high temperature gas-cooled reactor(HTGR).To solve the problem,a material performance test apparatus was built to provide reliable materials and technical support for relevant experiments of the HTGR.The apparatus uses a center high-purity graphite heater and surrounding thermal insulating layers made of carbon fiber felt to form a strong carbon reducing atmosphere inside the apparatus.Specially designed tungsten rhenium thermocouples which can endure high temperatures in carbonaceous atmospheres are used to control the temperature field.A typical experimental process was analyzed in the paper,which lasted 76 hours including seven stages.Experimental results showed the test apparatus could completely simulate the carbon reduction atmosphere and high temperature environment the same as that confronted in the real reactor and the performance of screened materials had been successfully tested and verified.Test temperature in the apparatus could be elevated up to 1600oC,which covered the whole temperature range of the normal operation and accident condition of HTGR and could fully meet the test requirements of materials used in the reactor. 展开更多
关键词 高温气冷反应堆 性能测试装置 屏蔽材料 设计 性能试验装置 高温气冷堆 还原气氛 实验过程
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Analysis on thermophoretic deposit of fine particle on water wall of 10 MW high temperature gas-cooled reactor 被引量:1
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作者 ZHOUTao YANGRui-Chang JIADou-Nan 《Nuclear Science and Techniques》 SCIE CAS CSCD 2005年第1期46-52,共7页
The water wall is an important part of the passive natural circulation residual heat removal system in a high temperature gas-cooled reactor. The maximum temperatures of the pressure shell and the water wall are calcu... The water wall is an important part of the passive natural circulation residual heat removal system in a high temperature gas-cooled reactor. The maximum temperatures of the pressure shell and the water wall are calcu- lated using annular vertical closed cavity model. Fine particles can deposit on the water wall due to the thermophore- sis effect. This deposit can affect heat transfer. The thermophoretic deposit efficiency is calculated by using Batch and Shen’s formula fitted for both laminar flow and turbulent flow. The calculated results indicate that natural convection is turbulent in the closed cavity. The transient thermophoretic deposit efficiency rises with the increase of the pressure shell’s temperature. Its maximum value is 14%. 展开更多
关键词 高温气冷反应堆 压水堆 放射性微粒 热敏致电沉积 安全防护
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Study on neutronics design of ordered-pebble-bed fluoride-salt- cooled high-temperature experimental reactor 被引量:3
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作者 Rui Yan Shi-He Yu +11 位作者 Yang Zou Qun Yang Bo Zhou Pu Yang Hong-Hua Peng Ya-Fen Liu Ye Dai Rui-Ming Ji Xu-Zhong Kang Xing-Wei Chen Ming-Hai Li Xiao-Han Yu 《Nuclear Science and Techniques》 SCIE CAS CSCD 2018年第6期36-44,共9页
This paper presents a neutronics design of a 10 MW ordered-pebble-bed fluoride-salt-cooled high-temperature experimental reactor. Through delicate layout, a core with ordered arranged pebble bed can be formed,which ca... This paper presents a neutronics design of a 10 MW ordered-pebble-bed fluoride-salt-cooled high-temperature experimental reactor. Through delicate layout, a core with ordered arranged pebble bed can be formed,which can keep core stability and meet the space requirements for thermal hydraulics and neutronics measurements.Overall, objectives of the core include inherent safety and sufficient excess reactivity providing 120 effective full power days for experiments. Considering the requirements above, the reactive control system is designed to consist of 16 control rods distributed in the graphite reflector. Combining the large control rods worth about 18000–20000 pcm, molten salt drain supplementary means(-6980 to -3651 pcm) and negative temperature coefficient(-6.32 to -3.80 pcm/K) feedback of the whole core, the reactor can realize sufficient shutdown margin and safety under steady state. Besides, some main physical properties, such as reactivity control, neutron spectrum and flux, power density distribution, and reactivity coefficient,have been calculated and analyzed in this study. In addition, some special problems in molten salt coolant are also considered, including ~6Li depletion and tritium production. 展开更多
关键词 中子物理学 反应堆 试验性 高温度 学习 设计 脉冲编码调制 控制系统
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Framework analysis of fluoride salt-cooled high temperature reactor probabilistic safety assessment 被引量:1
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作者 左嘉旭 靖剑平 +2 位作者 毕金生 宋维 陈堃 《Nuclear Science and Techniques》 SCIE CAS CSCD 2015年第5期112-117,共6页
Probabilistic safety assessment(PSA) is important in nuclear safety review and analysis. Because the design and physics of the fluoride salt-cooled high temperature reactor(FHR) differ greatly from the pressurized wat... Probabilistic safety assessment(PSA) is important in nuclear safety review and analysis. Because the design and physics of the fluoride salt-cooled high temperature reactor(FHR) differ greatly from the pressurized water reactor(PWR), the methods and steps of PSA in FHR should be studied. The high-temperature gascooled reactor(HTR-PM) and sodium-cooled fast reactors have built the PSA framework, and the framework to finish the PSA analysis. The FHR is compared with the PWR, HTR-PM and sodium-cooled fast reactors from the physics, design and safety. The PSA framework of FHR is discussed. In the FHR, the fuel and coolant combination provides large thermal margins to fuel damage(hundreds of degrees centigrade). The tristructuralisotropic(TRISO) as the fuel is independent in FHR core and its failure is limited for the core. The core damage in Level 1 PSA is of lower frequency. Levels 1 and 2 PSA are combined in the FHR PSA analysis. The initiating events analysis is the beginning, and the source term analysis and the release types are the target. Finally, Level3 PSA is done. 展开更多
关键词 高温气冷堆 概率安全评价 压水反应堆 框架分析 安全评估 氟盐 快中子反应堆 物理设计
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Thermal Performance Test of the Hot Gas Duct of10MW High Temperature Reactor Test Modulegh
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作者 姚梅生 《High Technology Letters》 EI CAS 1998年第1期107-112,共6页
he thermal performance test of the horizontal coaxial double tube hot gas duct (HGD) with an internal thermal insulation for the 10MW High Temperature Reactor Test Module (HTR10) was conducted on a Helium Test Loop(HE... he thermal performance test of the horizontal coaxial double tube hot gas duct (HGD) with an internal thermal insulation for the 10MW High Temperature Reactor Test Module (HTR10) was conducted on a Helium Test Loop(HETL). The present paper deals with the technical feature of the HETL, the test section and the thermal performance test of the HGD. The HGD test section with a triple tube structure includes an inner heater, a HGD model and a coldhot gas mixer. A counterflow of cold and hot helium gas under the pressure of about 3.0 MPa and the minimum temperature of 100℃ in the annular passage and the maximum of 950℃ in the central tube of the HGD model was formed. The HGD model was undergone 20 times of pressure cycle test under the pressure ranging from 0.1 to 3.4 MPa, 18 times of the temperature cycle test under the temperature ranging from 100 to 950℃ and high temperature (700 to 950℃) helium flow test for a period of more than 350 hours. The effective thermal conductivity (λeff) of the internal insulation of the HGD was investigated experimentally. The relationship of the effective thermal conductivity with the average tmperature of the internal insulation layer is λeff(W/m/℃)=0.3512+0.0003T(℃). The test results indicate that the HGD model has good abilities to resist heat flux from the central tube to the annular passage, temperature variations, and pressure variations. 展开更多
关键词 high temperature gascooled reactor Helium loop Hot gas duct high temperature performance test
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Gearbox Scheme in High Temperature Reactor Helium Gas Turbine System
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作者 Sheng Liu Xuanyu Sheng 《World Journal of Nuclear Science and Technology》 2012年第3期85-88,共4页
Helium Turbine is used in High Temperature Reactor Helium Gas Turbine (HTR-GT) system, by which the direct helium circulation between the reactor and turbine generator system will come true. Between helium turbine and... Helium Turbine is used in High Temperature Reactor Helium Gas Turbine (HTR-GT) system, by which the direct helium circulation between the reactor and turbine generator system will come true. Between helium turbine and generator, there is gearbox device which reduces the turbine rotation speed to normal speed required by the generator. Three optional gearbox schemes are discussed. The first is single reduction cylindrical gearbox, which consists of one high speed gear and one low speed gear. Its advantage is simple structure, easy to manufacture, and high reliability, while its disadvantage is large volume and misalignment of input and output axle. The second is planetary gear mechanism with static planet carrier. The third is planetary gear mechanism with static internal gear. The latter two gearbox devices have similar structure. Their advantage is small volume and high reduction gear ratio, while disadvantage are complicated structure, many gears, low reliability and low mechanical efficiency. 展开更多
关键词 high temperature gas cooled reactor GEAR BOX PLANETARY GEAR
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高温气冷堆热态功能试验中一回路加热动态特性研究
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作者 刘俊峰 王成龙 +4 位作者 秋穗正 李文姝 苏光辉 田文喜 马晓珑 《核科学与工程》 CAS CSCD 北大核心 2024年第2期295-301,共7页
高温气冷堆反应堆压力容器堆内构件由石墨和碳化硼烧结陶瓷材料组成,热态功能试验过程中需对一回路堆内构件进行加热除湿。针对高温气冷堆一回路热试系统特点,采用COMSOL Multiphysics 5.4计算软件构建了压力容器、蒸汽发生器和主氦风... 高温气冷堆反应堆压力容器堆内构件由石墨和碳化硼烧结陶瓷材料组成,热态功能试验过程中需对一回路堆内构件进行加热除湿。针对高温气冷堆一回路热试系统特点,采用COMSOL Multiphysics 5.4计算软件构建了压力容器、蒸汽发生器和主氦风机三维数值模型,并通过示范工程加热试验值验证了模型的可靠性,并获得了一回路加热过程中温度场动态特性。为了解决高温气冷堆示范工程一回路首次加热效率低的问题,提出了将辅助蒸汽通入到蒸汽发生器,并动态调整辅助蒸汽运行参数来加热一回路氦气的方法,结果表明:相较于主氦风机单独加热方式,外加辅助蒸汽热源可节省加热时间约31.3 h,同时可将堆芯最终平衡温度由250℃提高至265℃;在满足运行准则的前提下,更有利于碳砖和石墨堆内构件的除湿。该研究结果为高温气冷堆一回路热试提供了有力支持。 展开更多
关键词 高温气冷堆 主氦风机 辅助蒸汽 一回路加热 仿真试验
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清华大学核研院研制5 MW低温核供热试验堆与10 MW高温气冷实验堆的工程技术创新 被引量:1
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作者 游战洪 刘年凯 《工程研究(跨学科视野中的工程)》 2024年第3期354-363,共10页
清华大学核能与新能源技术研究院(简称核研院)先后在1989年和2000年建成了5 MW低温核供热试验堆与10 MW高温气冷实验堆。在建堆过程中,清华大学核研院坚持设计创新与工具创新、工艺创新、工序创新密切结合,完成了一系列关键设备和零部... 清华大学核能与新能源技术研究院(简称核研院)先后在1989年和2000年建成了5 MW低温核供热试验堆与10 MW高温气冷实验堆。在建堆过程中,清华大学核研院坚持设计创新与工具创新、工艺创新、工序创新密切结合,完成了一系列关键设备和零部件的制造与安装,使得整个工程项目顺利完工。在工程史研究中,技术工人做出的创新贡献并未引起学术界足够重视。本文表明,技术工人在工具、工艺、工序、制造与安装阶段的技术创新,亦是工程创新的重要保证。 展开更多
关键词 清华大学核研院 5 MW低温核供热试验堆 10 MW高温气冷实验堆 工程技术创新
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高温气冷堆主氦风机变阻力工况调试方法
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作者 叶林 严义杰 +4 位作者 徐伟强 赵峰 陈光建 李超 朱英杰 《强激光与粒子束》 CAS CSCD 北大核心 2024年第7期99-105,共7页
高温气冷堆主氦风机调试期间,由于一回路阻力低于设计工况,因而主氦风机无法完成全转速范围性能测试。基于主氦风机的理论特性与相似原理开发主氦风机不同阻力工况调试参数的推算方法。结合主氦风机单体试验工况点,准确推算主氦风机冷... 高温气冷堆主氦风机调试期间,由于一回路阻力低于设计工况,因而主氦风机无法完成全转速范围性能测试。基于主氦风机的理论特性与相似原理开发主氦风机不同阻力工况调试参数的推算方法。结合主氦风机单体试验工况点,准确推算主氦风机冷态与热态性能试验的工况点参数,并指导完成高温气冷堆主氦风机全转速、满功率性能测试。通过对主氦风机调试与出厂试验结果的对比分析,验证本推算方法的可行性,并给出空气介质与氦气介质工况转换的修正因子。通过主氦风机调试与运行数据的对比分析,可以看出本文提供的主氦风机调试工况具有足够的包络性,能够覆盖高温气冷堆运行期间主氦风机的所有运行工况,证明了本文提供的变阻力工况主氦风机调试方法满足高温气冷堆主氦风机性能验证需求,可用于指导后续高温气冷堆的主氦风机调试工作。 展开更多
关键词 变阻力工况 相似原理 主氦风机 性能测试 高温气冷堆
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氦气风机驱动电机转子径向通风结构研究
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作者 陶大军 孟卓然 +1 位作者 徐金燕 戈宝军 《电机与控制学报》 EI CSCD 北大核心 2024年第3期96-109,共14页
氦气风机驱动电机是高温气冷堆一回路唯一能动设备,其安全性直接影响到高温气冷堆的安全稳定运行。针对高温高压环境及氦气传热工质对驱动电机风路结构设计及相关参数影响引发的新问题,通过建立双侧转子铁心三维风路结构流固耦合传热模... 氦气风机驱动电机是高温气冷堆一回路唯一能动设备,其安全性直接影响到高温气冷堆的安全稳定运行。针对高温高压环境及氦气传热工质对驱动电机风路结构设计及相关参数影响引发的新问题,通过建立双侧转子铁心三维风路结构流固耦合传热模型,计算分析了高温高压环境下传热工质氦气在转子径向风沟内的流动特性,研究了转子分别在动态和静态情况下,通风结构内流体流动规律及转子铁心和导条的温升变化规律。同时,对不同种类传热工质的对应规律进行了对比研究,搭建了模拟实验测试装置,实测数据与数值计算结果吻合较好,验证了计算分析结果的合理性和正确性,为氦气风机驱动电机转子风路结构优化、冷却性能的有效提升提供一定的理论参考。 展开更多
关键词 高温气冷堆 氦气风机驱动电机 通风结构 传热特性 流固耦合
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双碳目标下高温气冷堆替代中小型火电的思考
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作者 张浩 王建建 +1 位作者 赵文军 武婷婷 《核安全》 2024年第3期70-74,共5页
碳达峰碳中和是我国一项重要的国家战略决策,“双碳”目标的提出给能源行业带来了深刻的变革,我国能源结构将进一步优化,电力行业必须实现低碳转型,新能源取代火电已成为必然。本文分析了新形势下火电企业面临的巨大挑战、发电规模受到... 碳达峰碳中和是我国一项重要的国家战略决策,“双碳”目标的提出给能源行业带来了深刻的变革,我国能源结构将进一步优化,电力行业必须实现低碳转型,新能源取代火电已成为必然。本文分析了新形势下火电企业面临的巨大挑战、发电规模受到限制、经营成本不断上升,尤其是中小型火电机组,面临着淘汰和关停的局面,而高温气冷堆具有固有安全性、发电效率高、用途广泛的显著特点,使其替代中小型火电成为可能。本文通过厂址适应性、技术可行性、经济可行性三方面,分析了高温气冷堆替代中小型火电的可行性,并从相关法律法规适用性、内陆厂址所带来的问题、开展公众沟通等方面提出建议。 展开更多
关键词 碳达峰碳中和 中小型火电 高温气冷堆 替代
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HTR-PM汽轮机轴封蒸汽断供原因分析及解决方案
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作者 叶林 姚尧 +4 位作者 马喜强 黄鹏 王磊 赵敬锴 崔鹏 《发电设备》 2024年第3期161-164,171,共5页
介绍了高温气冷堆示范工程(HTR-PM)汽轮机轴封系统,并且对轴封蒸汽断供的原因进行了分析,提出了可以采用蒸汽发生器及管道内余汽供轴封、辅助电锅炉至轴封供汽管道改造、高温空气供轴封这3种解决方案。对3种方案进行对比,分析其在成本... 介绍了高温气冷堆示范工程(HTR-PM)汽轮机轴封系统,并且对轴封蒸汽断供的原因进行了分析,提出了可以采用蒸汽发生器及管道内余汽供轴封、辅助电锅炉至轴封供汽管道改造、高温空气供轴封这3种解决方案。对3种方案进行对比,分析其在成本、可靠性和运行限制方面的优缺点,结果表明3种方案均是可行的。研究结果为HTR-PM汽轮机轴封蒸汽断供问题的解决提供了参考。 展开更多
关键词 高温气冷堆 轴封 蒸汽断供 余汽 高温空气
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温差热电转换型空间热管冷却反应堆瞬态分析程序开发及验证 被引量:1
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作者 葛攀和 李敏 +2 位作者 李杨柳 胡古 柯国土 《原子能科学技术》 EI CSCD 北大核心 2024年第1期69-83,共15页
热管冷却反应堆采用固态堆芯设计、高温热管传热,具有结构简单、非能动、高可靠性等优点。为研究温差热电转换型空间热管冷却反应堆电源系统的瞬态特性,本文针对该型电源系统中最主要的系统(包括堆本体、高温热管、温差热电转换系统)建... 热管冷却反应堆采用固态堆芯设计、高温热管传热,具有结构简单、非能动、高可靠性等优点。为研究温差热电转换型空间热管冷却反应堆电源系统的瞬态特性,本文针对该型电源系统中最主要的系统(包括堆本体、高温热管、温差热电转换系统)建立了详细的数学物理模型,并开发了系统瞬态分析程序,其中堆本体模型基于OpenFOAM进行模块开发,耦合了点堆动力学模型和反应性反馈模型。通过文献和试验数据分别验证了高温热管及温差热电转换模型,结果与参考值符合较好,其中温差热电转换模块发电功率与试验值的相对偏差小于2.75%。采用该程序对KRUSTY进行了建模分析,开展了反应性引入、热电转换模块失效、负荷跟踪、主动冷却丧失工况下的瞬态分析,并与试验值进行了对比。结果表明,在上述瞬态工况下堆芯燃料表面温度与试验值的偏差小于4.1 K,程序计算结果与试验值符合较好。 展开更多
关键词 热管冷却反应堆 瞬态分析 高温热管 温差热电转换 KRUSTY试验
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Simultaneous approach for simulation of a high-temperature gas-cooled reactor 被引量:2
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作者 Yang CHEN Jiang-hong YOU Zhi-jiang SHAO Ke-xin WANG Ji-xin QIAN 《Journal of Zhejiang University-Science A(Applied Physics & Engineering)》 SCIE EI CAS CSCD 2011年第7期567-574,共8页
The simulation of a high-temperature gas-cooled reactor pebble-bed module(HTR-PM) plant is discussed.This lumped parameter model has the form of a set differential algebraic equations(DAEs) that include stiff equation... The simulation of a high-temperature gas-cooled reactor pebble-bed module(HTR-PM) plant is discussed.This lumped parameter model has the form of a set differential algebraic equations(DAEs) that include stiff equations to model point neutron kinetics.The nested approach is the most common method to solve DAE,but this approach is very expensive and time-consuming due to inner iterations.This paper deals with an alternative approach in which a simultaneous solution method is used.The DAEs are discretized over a time horizon using collocation on finite elements,and Radau collocation points are applied.The resulting nonlinear algebraic equations can be solved by existing solvers.The discrete algorithm is discussed in detail;both accuracy and stability issues are considered.Finally,the simulation results are presented to validate the efficiency and accuracy of the simultaneous approach that takes much less time than the nested one. 展开更多
关键词 Differential algebraic equations(DAEs) high-temperature gas-cooled reactor(HTR) SIMULATION Simultaneous approach
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一种简化的高温热管启动模型 被引量:1
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作者 王政 苟军利 +1 位作者 徐世浩 单建强 《原子能科学技术》 EI CSCD 北大核心 2024年第1期84-92,共9页
热管堆具有体积小、结构紧凑、功率密度高和固有安全性好等优点,被认为是深空和深海任务中最有前途的候选之一。为了研究其启动特性,建立兼顾计算精度及求解效率的热管启动模型至关重要。本文在充分考虑吸液芯区工质的熔化及气液界面处... 热管堆具有体积小、结构紧凑、功率密度高和固有安全性好等优点,被认为是深空和深海任务中最有前途的候选之一。为了研究其启动特性,建立兼顾计算精度及求解效率的热管启动模型至关重要。本文在充分考虑吸液芯区工质的熔化及气液界面处的蒸发和冷凝现象的基础上,建立了基于二维导热的热管壁和吸液芯区热阻网络模型。对于蒸汽区,基于尘气模型(DGM),研究分析了两种不同模拟方式的求解精度和计算效率。通过对不同碱金属热管实验的模拟,验证了模型的准确性。结果表明,模型能较好地模拟高温热管的启动特性,简化的等效热阻模型具有更高的计算效率,其更适合于热管堆系统的启动特性模拟。 展开更多
关键词 热管堆 启动特性 高温热管 等效热阻模型
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Safety Features of Modular High Temperature Gas-cooled Reactors (MHTGR) 被引量:1
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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
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Self-acting Afterheat Removal in High Temperature Gas Cooled Reactors
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作者 Kugeler K.,Phlippen P.W.,Nieβen H.F. Institute for Safety Research and Reactor Technology, Research Center Jülich,Jülich D 52428, Germany 《Tsinghua Science and Technology》 SCIE EI CAS 1998年第4期1167-1178,共12页
Much more nuclear energy capacity is needed than currently installed to meet the demand of energy and the requirement on environment protection in the next decades. More stringent nuclear safety standards have to be e... Much more nuclear energy capacity is needed than currently installed to meet the demand of energy and the requirement on environment protection in the next decades. More stringent nuclear safety standards have to be established for future nuclear power plants.The philosophy of a catastrophe free nuclear technology is presented in this paper. The issue of afterheat removal of high temperature gas cooled reactors is handled.It is a striking inherent safety feature of the modular high temperature gas cooled reactor design that the afterheat removal takes place without any active core cooling systems. 展开更多
关键词 nuclear safety afterheat high temperature gas cooled reactors
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空间热管反应堆电源研究进展及展望
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作者 刘逍 王宁 +5 位作者 张开远 齐敏 李仲春 张卓华 谢细明 柴晓明 《火箭推进》 CAS 北大核心 2024年第4期66-75,共10页
深空探测技术的发展对动力系统提出了更高的要求。传统的太阳能电源与化学电源的适用范围较小,环境适应能力不强,而微型核反应堆电源能量密度高,不依赖太阳光照,可应用于轨道运输、高轨探测多场景任务。在微型核反应堆电源技术路线中,... 深空探测技术的发展对动力系统提出了更高的要求。传统的太阳能电源与化学电源的适用范围较小,环境适应能力不强,而微型核反应堆电源能量密度高,不依赖太阳光照,可应用于轨道运输、高轨探测多场景任务。在微型核反应堆电源技术路线中,热管冷却核反应堆电源因其系统设备极大简化、模块化设计,高可靠的全固态堆芯、非能动传热及瞬态响应迅速等特性,成为空间核反应堆电源最具可行性的路线之一。通过文献调研总结目前空间热管堆发展现状,从发展历史出发,梳理热管冷却核反应堆电源设计和理论研究,总结热管冷却核反应堆电源发展方向和关键技术。 展开更多
关键词 空间动力 核电源 热管反应堆 高温热管
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