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High-precision and wide-range real-time neutron flux monitor system through multipoint linear calibration 被引量:3
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作者 Ren-Jie Zhu Xiang Zhou +9 位作者 Zi-Hao Liu Wen-Di Wang Xiao-Li Mou Teng-Fei Fang Qing-Li Ma Xiu-Feng Xu Guo-Liang Yuan Li Zhao Ling-Feng Wei Ze-Jie Yin 《Nuclear Science and Techniques》 SCIE CAS CSCD 2020年第9期98-106,共9页
The neutron flux monitor(NFM)system is an important diagnostic subsystem introduced by large nuclear fusion devices such as international thermonuclear experimental reactor(ITER),Japan torus-60,tokamak fusion test rea... The neutron flux monitor(NFM)system is an important diagnostic subsystem introduced by large nuclear fusion devices such as international thermonuclear experimental reactor(ITER),Japan torus-60,tokamak fusion test reactor,and HL-2 A.Neutron fluxes can provide real-time parameters for nuclear fusion,including neutron source intensity and fusion power.Corresponding to different nuclear reaction periods,neutron fluxes span over seven decades,thereby requiring electronic devices to operate in counting and Campbelling modes simultaneously.Therefore,it is crucial to design a real-time NFM system to encompass such a wide dynamic range.In this study,a high-precision NFM system with a wide measurement range of neutron flux is implemented using realtime multipoint linear calibration.It can automatically switch between counting and Campbelling modes with variations in the neutron flux.We established a testing platform to verify the feasibility of the NFM system,which can output the simulated neutron signal using an arbitrary waveform generator.Meanwhile,the accurate calibration interval of the Campbelling mode is defined well.Based on the above-mentioned design,the system satisfies the requirements,offering a dynamic range of 10~8 cps,temporal resolution of 1 ms,and maximal relative error of 4%measured at the signal-to-noise ratio of 15.8 dB.Additionally,the NFM system is verified in a field experiment involving HL-2 A,and the measured neutron flux is consistent with the results. 展开更多
关键词 Multipoint linear calibration Real time Simulated neutron signal neutron flux monitoring ITER HL-2A
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Development of Prototype Neutron Flux Monitor for ITER 被引量:1
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作者 杨进蔚 宋先瑛 +6 位作者 张炜 李旭 郦文忠 王世庆 肖功珊 杨波 陆双桐 《Plasma Science and Technology》 SCIE EI CAS CSCD 2005年第3期2860-2862,共3页
The prototype neutron flux monitor consists of a high purity 235U fission chamber detector and a 'blank' detector, which is a fissile material free detector with the same dimension as the fission chamber detec... The prototype neutron flux monitor consists of a high purity 235U fission chamber detector and a 'blank' detector, which is a fissile material free detector with the same dimension as the fission chamber detector to identify noise issues such as noise coming from gamma rays. The main parameters of the fission chamber assembly that have been measured in the laboratory are confirmed to approach the technological level of the International Thermonuclear Experimental Reactor (ITER) in the near future. This prototype neutron flux monitor will be further developed to become a neutron flux monitor suitable for the operation phase of D-D fusion on the ITER. 展开更多
关键词 neutron flux monitor fission chamber detector international thermonuclear experimental reactor (ITER) plateau characteristic curve discrimination threshold
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Development of a wide-range and fast-response digitizing pulse signal acquisition and processing system for neutron flux monitoring on EAST 被引量:1
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作者 Li Yang Hong-Rui Cao +7 位作者 Jin-Long Zhao Zi-Han Zhang Qiang Li Guo-Bin Wu Yong-Qiang Zhang Guo-Qiang Zhong Li-Qun Hu Zi-Jun Zhang 《Nuclear Science and Techniques》 SCIE EI CAS CSCD 2022年第3期126-136,共11页
The neutron count rate fluctuation reaches six orders of magnitude between the ohmic plasma scenario and high power of auxiliary heating on an experimental advanced superconducting tokamak(EAST).The measurement result... The neutron count rate fluctuation reaches six orders of magnitude between the ohmic plasma scenario and high power of auxiliary heating on an experimental advanced superconducting tokamak(EAST).The measurement result of neutron flux monitoring(NFM)is a significant feedback parameter related to the acquisition of radiation protection-related information and rapid fluctuations in neutron emission induced by plasma magnetohydrodynamic activity.Therefore,a wide range and high time resolution are required for the NFM system on EAST.To satisfy these requirements,a digital pulse signal acquisition and processing system with a wide dynamic range and fast response time was developed.The present study was conducted using a field-programmable gate array(FPGA)and peripheral component interconnect extension for instrument express(PXIe)platform.The digital dual measurement modes,which are composed of the pulse-counting mode and AC coupled square integral's Campbelling mode,were designed to expand the measurement range of the signal acquisition and processing system.The time resolution of the signal acquisition and processing system was improved from 10 to 1 ms owing to utilizing highspeed analog-to-digital converters(ADCs),a high-speed PXIe communication with a direct memory access(DMA)mode,and online data preprocessing technology of FPGA.The signal acquisition and processing system was tested experimentally in the EAST radiation field.The test results showed that the time resolution of NFM was improved to 1 ms,and the dynamic range of the neutron counts rate was expanded to more than 10^(6) counts per second.The Campbelling mode was calibrated using a multipoint average linear fitting method;subsequently,the fitting coefficient reached 0.9911.Therefore,the newly developed pulse signal acquisition and processing system ensures that the NFM system meets the requirements of high-parameter experiments conducted on EAST more effectively. 展开更多
关键词 EAST neutron flux monitoring High time resolution Wide range Pulse signal acquisition and processing system
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Fusion Neutron Flux Monitor for ITER 被引量:1
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作者 杨进蔚 杨青巍 +3 位作者 肖功珊 张炜 宋先瑛 李旭 《Plasma Science and Technology》 SCIE EI CAS CSCD 2008年第2期141-147,共7页
Neutron flux monitor (NFM) as an important diagnostic sub-system in ITER (international thermonuclear experimental reactor) provides a global neutron source intensity, fusion power and neutron flux in real time. T... Neutron flux monitor (NFM) as an important diagnostic sub-system in ITER (international thermonuclear experimental reactor) provides a global neutron source intensity, fusion power and neutron flux in real time. Three types of neutron flux monitor assemblies with different sensitivities and shielding materials have been designed. Through MCNP (Mante-Carlo neutral particle transport code) calculations, this extended system of NFM can detect the neutron flux in a range of 10^4 n/(cm^2.s) to 10^14 n/(cm^2.s). It is capable of providing accurate neutron yield measurements for all operational modes encountered in the ITER experiments including the in-situ calibration. Combining both the counting mode and Campbelling (MSV; Mean Square Voltage) mode in the signal processing units, the requirement of the dynamic range (107) for these NFMs and time resolution (1 ms) can be met. Based on a uncertainty analysis, the estimated absolute measurement accuracies of the total fusion neutron yield can reach the required 10% level in both the early stage of the DD-phase and the DD-phase, the absolute measurement accuracy full power DT operation mode. In the advanced would be better than 20%. 展开更多
关键词 neutron flux monitor international thermonuclear experimental reactor(ITER) assembly of fission chamber
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Development of a data acquisition and control system for the International Thermonuclear Experimental Reactor neutron flux monitor 被引量:1
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作者 刘子豪 周翔 +3 位作者 朱仁杰 赵丽 魏凌峰 阴泽杰 《Plasma Science and Technology》 SCIE EI CAS CSCD 2020年第1期96-103,共8页
To satisfy high-precision,widc-rangc,and real-time neutron flux measurement requirements by the International Thermonuclear Experimental Reactor(ITF.R),a data acquisition and control system based on fission chamber de... To satisfy high-precision,widc-rangc,and real-time neutron flux measurement requirements by the International Thermonuclear Experimental Reactor(ITF.R),a data acquisition and control system based on fission chamber detectors and fast controller technology,has been developed for neutron flux monitor in ITER Equatorial Port#7.The signal processing units which arc based on a field programmable gate array and the PXI Express platform arc designed to realize the neutron flux measurement with I ms time resolution and a fast response less than 0.2 ms,together with real-time timestamps provided by a timing hoard.The application of the wide-range algorithm allows the system to measure up to 10^10cps with a relative error of less than 5%.Furthermore,the system is managed and controlled by a software based on the Experimental Physics and Industrial Control System,compliant with COntrol.Data Access and Communication architecture. 展开更多
关键词 neutron flux monitor data acquisition.CODAC F.PICS
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Dynamic linear calibration method for a wide range neutron flux monitor system in ITER 被引量:3
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作者 LI Shiping XU Xiufeng +2 位作者 CAO Hongrui YANG Qingwei YIN Zejie 《Nuclear Science and Techniques》 SCIE CAS CSCD 2013年第4期57-60,共4页
As a key part of the diagnosis system in the International Thermonuclear Experimental Reactor(ITER),the neutron flux monitor(NFM),which measures the neutron intensity of the fusion reaction,is a Counting-Campbelling s... As a key part of the diagnosis system in the International Thermonuclear Experimental Reactor(ITER),the neutron flux monitor(NFM),which measures the neutron intensity of the fusion reaction,is a Counting-Campbelling system with a large dynamic counting range.A dynamic linear calibration method is proposed in this paper to solve the problem of cross-over between the different counting and Campbelling channels,and improve the accuracy of the cross-calibration for long-term operation.The experimental results show that the NFM system with the dynamic linear calibration system can obtain the neutron flux of the fusion reactor in real time and realize the seamless measurement area connection between the two channels. 展开更多
关键词 动态非线性 监测系统 中子通量 校正方法 ITER 国际热核实验反应堆 聚变反应堆 组成部分
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Real-time wide-range neutron flux monitor for thorium-based molten salt reactor
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作者 Xiang Zhou Zi-Hao Liu +2 位作者 Chao Chen Guo-Qing Huang Ze-Jie Yin 《Nuclear Science and Techniques》 SCIE CAS CSCD 2018年第8期107-113,共7页
A novel full-digital real-time neutron flux monitor(NFM) has been developed for thorium-based molten salt reactor(TMSR).The system is based on the highspeed,parallel,and pipeline processing of the field programmable g... A novel full-digital real-time neutron flux monitor(NFM) has been developed for thorium-based molten salt reactor(TMSR).The system is based on the highspeed,parallel,and pipeline processing of the field programmable gate array as well as the high-stability controller area network platform.A measurement range of 10~8 counts per second is achieved with a single fission chamber by utilizing the normalization of the count and Campbell algorithms.With the advantages of using the measurement range,system integrity,and real-time performance,digital NFM has been tested in the Xi'an pulsed reactor fission experiments and was found to exhibit superior experimental performance. 展开更多
关键词 监视器 反应堆 流动 中子 熔融 宽范围 控制器区域网络 实时
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田湾核电站换料期间中子通量密度监测方式优化研究
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作者 吕牛 李东朋 +1 位作者 夏兆东 王杨 《原子能科学技术》 EI CAS CSCD 北大核心 2023年第1期140-146,共7页
针对田湾核电站换料期间中子通量密度监测方式的不足,研究了用源量程探测器取代换料监测量程探测器完成换料期间中子通量密度监测的优化方案。基于全进全出和堆芯倒料两种堆芯换料方式,应用蒙特卡罗程序MCNP模拟计算源量程探测器的响应... 针对田湾核电站换料期间中子通量密度监测方式的不足,研究了用源量程探测器取代换料监测量程探测器完成换料期间中子通量密度监测的优化方案。基于全进全出和堆芯倒料两种堆芯换料方式,应用蒙特卡罗程序MCNP模拟计算源量程探测器的响应,计算结果表明,当靠近源量程探测器位置的乏燃料组件达到一定燃耗深度时,源量程探测器中子计数率达到0.5 s^(-1),满足换料过程中子计数率监测要求,与测量值符合得很好。应用源量程探测器替代换料监测量程探测器监测换料期间中子通量密度是可行的。 展开更多
关键词 换料期间 探测器响应 中子通量密度监测
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压水堆堆芯中子通量监测系统对比研究
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作者 陈彦发 李袁鹏 +4 位作者 徐东 陈亮 高鸣 李亮 黄伟杰 《仪器仪表用户》 2023年第9期91-94,14,共5页
压水堆堆芯中子通量监测系统主要用于实现对反应堆堆芯的中子通量密度、冷却剂温度及液位的实时在线监测,对核电站的安全稳定运行起着至关重要的作用。通过介绍目前国内压水堆核电站主要堆型中堆芯中子通量监测系统的应用情况,对比分析... 压水堆堆芯中子通量监测系统主要用于实现对反应堆堆芯的中子通量密度、冷却剂温度及液位的实时在线监测,对核电站的安全稳定运行起着至关重要的作用。通过介绍目前国内压水堆核电站主要堆型中堆芯中子通量监测系统的应用情况,对比分析了该系统在结构组成、功能性能等方面的差异,为其优化设计提供借鉴。 展开更多
关键词 中子通量监测系统 堆芯 中子通量密度 冷却剂温度 压水堆核电站
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(极)年轻火山岩激光熔蚀^(40)Ar/^(39)Ar定年 被引量:10
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作者 周晶 季建清 +5 位作者 Alan DEINO 龚俊峰 韩宝福 涂继耀 桑海清 徐剑光 《岩石学报》 SCIE EI CAS CSCD 北大核心 2013年第8期2811-2825,共15页
对中国大量年轻或/和极年轻火山岩的定年实践研究表明,(极)年轻火山岩的激光熔蚀40Ar/39Ar定年具有不同于第四纪以前喷发火山岩定年的显著特点。激光熔蚀40Ar/39Ar定年技术因为本底低、样品用量小以及与现代惰性气体同位素质谱设备在灵... 对中国大量年轻或/和极年轻火山岩的定年实践研究表明,(极)年轻火山岩的激光熔蚀40Ar/39Ar定年具有不同于第四纪以前喷发火山岩定年的显著特点。激光熔蚀40Ar/39Ar定年技术因为本底低、样品用量小以及与现代惰性气体同位素质谱设备在灵敏度、高精度方面的相一致,在年轻火山岩的定年中得到深入运用。借助激光在年轻或/和极年轻火山岩的40Ar/39Ar定年中,实践证明,样品形成时限越年轻(特别是相当于第四纪时期的样品),Nier值与样品中初始氩比值的偏离会引起K-Ar和40Ar/39Ar表观年龄的偏差越大。对于小于0.2Ma的样品,Nier值与样品中初始氩比值的偏离对K-Ar和40Ar/39Ar表观年龄的偏差影响呈指数增长;当样品年龄相对较老(老于第四纪)时,Nier值和初始氩比值的偏离对K-Ar和40Ar/39Ar表观年龄的影响较小。以40Ar/39Ar定年为出发点,定量给出界定年轻与极年轻火山岩的年龄:2~0.2Ma的火山岩界定为年轻火山岩,0.2Ma以来的火山岩称为极年轻火山岩。实验结果还证实,测定(极)年轻火山岩基质年龄时要尽量剔除非同源分馏的斑晶,以便去除斑晶可能带来的过剩氩影响;年轻火山岩样品的测年,应根据岩石结构和粒度特征选取合适的粒度,通常情况下,推荐0.2mm颗粒直径(60~80目)为理想粒径;年轻火山岩样品在快中子辐照后冷却放置时间不宜过长,否则造成37Ar测不准,影响数据结果,带来较大偏差;激光40Ar/39Ar精细定年对标准样品的均一性有很高的要求,通过标定常用的国内外监测标样发现,标样SB-778-Bi,Bern4M,BT-1均一性很好,适合用作激光熔蚀40Ar/39Ar定年监测;测试数据的处理中,火山岩喷发后冷却结晶中同时形成的斑晶和基质的等时线处理能够帮助获得客观真实和精细的年龄结果。在此基础上,北京大学惰性气体同位素实验室建成了专用于(极)年轻火山岩精细定年的激光熔蚀40Ar/39Ar定年实验流程。 展开更多
关键词 激光40Ar 39Ar (极)年轻火山岩 监测标样 照射参数 斑晶基质等时线
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ITER中子通量监测器原型的研制 被引量:4
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作者 杨进蔚 张炜 +5 位作者 宋先瑛 李旭 郦文忠 王世庆 肖功珊 陆双桐 《核聚变与等离子体物理》 EI CAS CSCD 北大核心 2005年第2期105-109,共5页
研制的用于国际热核实验堆(ITER)的中子通量监测器由裂变室探测器组合构成,包括两只不同灵敏度的阴极上涂有高纯裂变材料235U的裂变室探测器和一只未涂裂变材料的'空白'探测器。此组合用于中子、γ射线、硬X射线的混合辐射场条... 研制的用于国际热核实验堆(ITER)的中子通量监测器由裂变室探测器组合构成,包括两只不同灵敏度的阴极上涂有高纯裂变材料235U的裂变室探测器和一只未涂裂变材料的'空白'探测器。此组合用于中子、γ射线、硬X射线的混合辐射场条件下对中子的测量,可完全扣除后两种辐射对中子通量测量的影响,提高测量精确度。探测器的电压坪长、坪宽、坪斜、计数坪特曲线及宽度、输出脉冲宽度和探测系统计数率等主要参数经测试已达到设计要求,部分参数(如计数率)已接近ITER近期的技术水平。通过提高相关材料的纯度、优化裂变室结构和采用Campbelling模式及高精度的信号选择器,可研制出适用于ITERD D聚变条件下(低聚变中子产额)的快中子通量监测器。 展开更多
关键词 ITER 监测器 研制 国际热核实验堆 原型 裂变材料 ^235U 混合辐射场 测量精确度 信号选择器 快中子通量 探测器 裂变室 硬X射线 设计要求 探测系统 脉冲宽度 相关材料 中子产额 计数率 灵敏度 γ射线 高精度 g模式 组合
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钒自给能探测器中子响应计算方法 被引量:7
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作者 毕光文 汤春桃 杨波 《核技术》 CAS CSCD 北大核心 2017年第6期89-94,共6页
钒自给能探测器被广泛用作核动力反应堆的堆内固定式探测器,为堆芯中子注量率分布测量连续不断地提供信息。研究钒自给能探测器的响应电流计算方法,为堆芯在线功率分布监测与探测器设计优化提供理论依据。首先描述钒自给能探测器的响应... 钒自给能探测器被广泛用作核动力反应堆的堆内固定式探测器,为堆芯中子注量率分布测量连续不断地提供信息。研究钒自给能探测器的响应电流计算方法,为堆芯在线功率分布监测与探测器设计优化提供理论依据。首先描述钒自给能探测器的响应机理与特性,然后基于Warren提出的理论模型,详细介绍中子响应电流控制方程及电子逃脱概率的计算方法,最后根据公开报道的典型钒探测器规格与实验数据进行数值模拟分析。结果显示,单位长度热中子灵敏度计算值与测量值相对偏差在±5%以内,论证了该方法的有效性与计算精度。 展开更多
关键词 钒自给能探测器 堆内中子注量率分布监测 探测器响应电流 电子逃脱概率 中子灵敏度
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数字化多通道宽量程ITER中子通量密度测量系统研制 被引量:1
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作者 吴军 袁晨 阴泽杰 《原子能科学技术》 EI CAS CSCD 北大核心 2017年第6期1071-1076,共6页
针对国际热核聚变实验堆(ITER)对中子通量密度测量宽量程、高集成度、实时性的要求,设计了一套基于PXI架构的多通道中子通量密度测量系统。该系统包括新研制的电流灵敏前置放大器及基于高速模数转换器(ADC)和可编程逻辑器件(FPGA)的主... 针对国际热核聚变实验堆(ITER)对中子通量密度测量宽量程、高集成度、实时性的要求,设计了一套基于PXI架构的多通道中子通量密度测量系统。该系统包括新研制的电流灵敏前置放大器及基于高速模数转换器(ADC)和可编程逻辑器件(FPGA)的主电子学插件。通过全数字化信号处理技术衔接脉冲计数和坎贝尔两种测量模式,大幅拓展了测量量程和提高了系统集成度。该系统通过使用脉冲堆积率估算算法,实现了测量模式的精确自动切换。实验结果表明,该系统具备单一裂变室大于1.7×10^(10)cm^(-2)·s^(-1)中子通量密度实时测量能力,全量程相对误差低于7.1%。 展开更多
关键词 ITER 反应堆监测 中子通量密度测量 信号采集与处理
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防城港核电站堆内中子通量测量系统指套管碰磨分析 被引量:8
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作者 胡建荣 罗婷 +3 位作者 简捷 刘才学 杨建东 李振 《核科学与工程》 CSCD 北大核心 2017年第5期750-755,共6页
防城港核电站1号机组主泵惰走试验期间,在对核电站松脱部件和振动监测系统13路加速度通道进行背景噪声例行检查时发现,通过松脱部件和振动监测系统的声音监听设备监测到,安装于反应堆压力容器底部堆内中子通量测量系统导向管上通道有&qu... 防城港核电站1号机组主泵惰走试验期间,在对核电站松脱部件和振动监测系统13路加速度通道进行背景噪声例行检查时发现,通过松脱部件和振动监测系统的声音监听设备监测到,安装于反应堆压力容器底部堆内中子通量测量系统导向管上通道有"哒哒哒"的异常信号。为找出异常信号源,利用松脱部件监测系统声监测功能对压力容器底部监测到的异常信号进行分析,该信号不是由松脱部件产生的信号。通过听音棒的辅助监听,最后综合分析得出该信号是由堆内中子通量测量系统指套管在管道路径上碰磨引起。该事件的分析与解决,不仅解决了工程建设需要,对核安全局批准下一步工作开展提供了支持依据,而且对通过松脱部件监测系统来开展由于流致振动引起的中子通量测量系统指套管异常振动诊断有重大的实用价值。 展开更多
关键词 核电站 堆内中子通量测量系统 松脱部件和振动监测系统 指套管 碰磨
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In-situ Calibration Techniques and Preliminary Assessment of Accuracy for NFM on ITER
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作者 杨进蔚 杨青巍 袁国良 《Plasma Science and Technology》 SCIE EI CAS CSCD 2008年第6期676-680,共5页
Absolutely calibrated measurements of the neutron yields which need to cover both D-D and D-T phase of the international thermal-nuclear experimental reactor (ITER) are important for the evaluation of fusion power a... Absolutely calibrated measurements of the neutron yields which need to cover both D-D and D-T phase of the international thermal-nuclear experimental reactor (ITER) are important for the evaluation of fusion power and fusion gain Q in D-D and D-T operations. This paper describes the in-situ calibration techniques and methods, the neutron sources including ^252Cf and neutron generator for calibration, the preliminary accuracy assessment and the error analyses. In addition, some difficult problems regarding the in situ calibration for the neutron flux monitor (NFM) on ITER are presented and discussed. 展开更多
关键词 in situ calibration neutron flux monitor neutron generator (NG)
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基于TDC-GP1测量前沿时间实现的n-γ脉冲甄别器
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作者 曹宏睿 吴军 +4 位作者 李世平 徐修峰 袁国梁 杨青巍 阴泽杰 《核电子学与探测技术》 CAS CSCD 北大核心 2013年第2期158-161,共4页
中子通量探测是国际热核聚变实验反应堆项目中一个关键性的测量课题,其难点在于如何有效地剔除聚变反应中伴生的α、γ等粒子及其他非中子信号,保留有用的中子信号,从而得到准确的中子通量。由于α、γ等粒子及其他非中子信号与中子信... 中子通量探测是国际热核聚变实验反应堆项目中一个关键性的测量课题,其难点在于如何有效地剔除聚变反应中伴生的α、γ等粒子及其他非中子信号,保留有用的中子信号,从而得到准确的中子通量。由于α、γ等粒子及其他非中子信号与中子信号在脉冲幅度和上升时间上均存在差别,根据这些特征设计的n-γ脉冲甄别器基于测量脉冲信号前沿上升时间,并辅以脉冲幅度甄别,实现了n-γ精确甄别。其中,上升时间测量是通过TDC-GP1配合双路恒比定时器实现的。经实验验证,此方法能够有效地识别中子信号并剔除α、γ信号等非中子信号的影响,n-γ脉冲甄别器探测中子信号计数率的动态范围可以达到0-106cps。 展开更多
关键词 n-γ脉冲甄别器 TDC-GP1 恒比定时器 中子通量监测器 国际热核聚变实验反应堆
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加速器驱动次临界反应堆次临界度测量方法研究 被引量:1
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作者 魏书成 蒋校丰 张少泓 《核科学与工程》 CSCD 北大核心 2008年第4期330-333,353,共5页
以IAEA ADS基准题和日本京都大学KUCA实验装置为对象,对作者提出的次临界度测量方法[1]进行了更广泛的可行性验证。结果表明:对于局部区域功率变化引起的小扰动,通过改进表征中子注量率空间分布的特征参数,该方法仍然具有高的精度;而对... 以IAEA ADS基准题和日本京都大学KUCA实验装置为对象,对作者提出的次临界度测量方法[1]进行了更广泛的可行性验证。结果表明:对于局部区域功率变化引起的小扰动,通过改进表征中子注量率空间分布的特征参数,该方法仍然具有高的精度;而对于控制棒插入引起的大扰动,通过引入修正因子的方法,也仍然能准确测量次临界度。 展开更多
关键词 ADS 次临界度监测 中子注量率空间分布 控制棒插入
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密封中子发生器中子通量的空间分布
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作者 张琳 《辽宁省交通高等专科学校学报》 1999年第2期15-16,共2页
被测装置为M_z—125型密封中子发生器。用纯度为99.9%园铜片作监测器。近靶处中子通量分布梯度较大,离靶6cm以远中子通量与离靶距离的关系符合反平方律。
关键词 密封中子发生器 14Mev中子 中子通量 空间分布
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