共查询到19条相似文献,搜索用时 125 毫秒
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首先简要介绍了核爆地震自动识别研究的历史和现状,重点介绍了笔者所在的研究集体的研究进展;然后.针对核爆地震自动识别研究的方法理论——模式识别中的几个关键问题进行了讨论,给出了初步研究结果,并提出了进一步研究设想。 相似文献
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放射性核素迁移研究的现状 总被引:2,自引:0,他引:2
杨明太 《核电子学与探测技术》2005,25(6):878-880
综述了放射性核素迁移研究的历史发展过程和现状,着重叙述了放射性核索迁移研究中,实验室模拟研究、天然类比研究、计算机模拟研究和示踪研究的方法及其进展。 相似文献
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本文论述了我国核化学基础研究的现状,重点介绍了裂变产物化学形态研究、裂变化学研究、裂变产物放化分离方法研究、长寿命核素核数据测量研究等领域的进展和展望.并结合我国核能发展的需要,展望了核化学研究的前景. 相似文献
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本文概述了研究堆定期安全审查(PSR)审评依据的确定,介绍了我国研究堆定期安全审查审评的实施情况及取得的成效,探讨了有关研究堆定期安全审查及其审评的若干问题,并提出了一些有关加强我国研究堆定期安全审查工作的建议。 相似文献
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核设施的设备老化控制研究策略 总被引:1,自引:0,他引:1
指出了核设施中普遍存在着设备老化问题,及设备老化控制研究的必要性.探讨了分层次开展设备老化控制研究的策略及各层次的研究思路,还对运用"生命周期评价”方法开展设备老化控制研究的可行性作了探讨. 相似文献
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苏联植物纤维原料辐射水解研究进展 总被引:2,自引:0,他引:2
本文对苏联近年植物纤维原料辐射水解的基础研究及应用研究作了概述,并介绍了本领域的技术经济现状。最后文中还指出了本项研究的发展前景及方向。 相似文献
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核电厂中流固耦合现象数值模拟研究综述 总被引:1,自引:1,他引:0
流固耦合现象在核电厂中广泛存在,该现象引起的结构动力学问题对核电厂结构完整性和安全性有重要影响。目前,国内外对核电厂中流固耦合现象的研究给予越来越多的关注。本文介绍华北电力大学在该方面的一些研究进展,例如,快堆燃料组件抗震分析新的流体附加质量计算方法研究;蒸汽发生器换热管双管漩涡脱落的数值模拟;一个先进堆燃料组件平行板上流动引起的漩涡脱落数值模拟;由地震引起的自由表面对快堆主容器冲击现象的研究;移动粒子法求解液面晃动及晃动引起离散现象的研究等。 相似文献
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β-γ混合辐射场测量中需要甄别入射到探测器中的粒子类型,旨在为进一步开展β/γ甄别和测量研究提供有价值的资料。论文概述并分析了粒子甄别方法及其原理,指出叠层闪烁探测器是最适合用于现场β/γ甄别和测量的解决方案。从探测器结构设计与判定方法和脉冲形状甄别算法两个角度回顾了利用叠层闪烁探测器甄别β/γ粒子的研究现状,指出现有研究中存在的一些问题,并对进一步研究提出相关改进建议。 相似文献
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第3代大型先进压水堆设置非能动余热排出系统,包括大容积高位水箱及其内置的非能动余热排出热交换器(PRHR HX)和自动降压系统(ADS)喷洒器,在运行过程中呈现出复杂的气液两相热工水力现象和独特的传热、传质特性。近年来随着非能动安全系统工程需求和相关研究的兴起,国内外开展了一些针对大容积非能动冷却水箱及其内置关键部件热工水力特性的相关研究,本文对上述问题的研究现状进行综述。对于PRHR HX,评价特殊C型管束在单相自然对流、两相沸腾条件下的传热特性,分析经典传热模型及改进经验关联式的适用性;对于ADS 1~3级喷洒器高温高压蒸汽喷放冷凝过程,综合分析其喷放冷凝流型、特征参数、冷凝换热系数等关键传热、传质特性。以上研究大幅丰富了第3代大型先进压水堆大容积水箱的设计理论,并进行了实际工程应用。本文在此基础上,对相关研究未来发展方向进行展望。 相似文献
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Muon physics and the application of muon technique is an interdisciplinary research which involves particle physics, material science, condensed matter physics, biomolecular science, and archaeology. Many important researches have been done and published in these areas by scientists from North America, Europe, and Japan. Due to the lack of accelerator-based muon source in China, Chinese research groups in these fields mainly rely on overseas muon facilities or on joining international collaborations. Some recent major progress on muon physics and muon technique application, and the prospects of the design, construction, and application of the accelerator-based muon source in China were reported in this paper. 相似文献
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Hideaki Saito Yutaka Murarnatsu Hideyasu Furukawa Shizuo Tsurumaki Nobuyuki Tanaka Takahiro Kei 《Nuclear Engineering and Design》1991,130(2)
This research relates to the application of a reinforced concrete containment vessel (RCCV) whose form can be freely selected to the development of an advanced BWR. The researchers on RCCVs are carried out recently, and good results are obtained. The RCCV employed in this research is different from conventional ones in structural elements and form. The purpose of this research is, therefore, to confirm the adequacy and reliability of the design method of the trial-designed RCCV, and to confirm the ultimate strengt and constructibleness. Basic, partial model and total model experiments were conducted.As a result of experimental and analytical studies, it was made sure that the trial-designed RCCV is safe and reliable at a design-load level. It was also confirmed that its ultimate strength fully ensures structural performance. Realizability was confirmed from consideration of the adequacy of the design method and constructibleness.This paper describes the results of the total model experiments planned for these researches. 相似文献
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Xiao Zejun Song Xianhui Lang Xuemei Bai Xuesong Ma Jieliang Wang Pengfei Chen Bingde 《Nuclear Engineering and Design》2004,229(2-3):213-222
One of the most important requirements in the design of pressurized water reactor (PWR) is to avoid the occurrence of critical heat flux (CHF). The design criteria for PWR specify that they must be operated at a certain percentage below CHF at all times and locations so as to the cladding temperature of fuel element at safe values. So in the process of safety assessment, CHF is one of important thermal-hydraulic parameters limiting the available power, whose size directly affects safety and economy of PWR nuclear power plant. This paper deals with a summary of experimental research progress on CHF of Chinese PWR. It mainly presents CHF experimental researches of Φ10 fuel assembly, CHF experimental researches of standard fuel assembly, and CHF experimental progress of non-uniform heated rod bundles. It should be emphasized that it also presents experimental research programs on CHF of Chinese advanced fuel assembly with self-reliance copyright. All CHF data obtained will be used for design improvement of Chinese PWR and R&D program of New Generation 1000 MWe PWR. 相似文献