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由于人因可靠性分析(HRA)方法中用于量化基本人因失误概率(HEP)的行为形成因子(PSF)数目众多,且一般是通过专家评判,从而带有主观性、模糊性和不确定性。本文提出一种利用相关系数矩阵、图的距离分类和主成分分析法相结合的方法构建核电厂数字化主控室操纵员PSF的评价模型,其目的是识别不同类型的人因事件中主要影响人因绩效的PSF,以供决策减少人因失误。对某核电厂的179起人因事件报告进行实验,结果表明该评价模型能对核电厂数字化主控室操纵员的PSF进行有效评价。 相似文献
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人因可靠性分析(HRA)已成为概率安全分析(PSA)必不可少的内容.事故前人因事件可靠性分析作为HRA的重要组成部分,对PSA最终计算结果有重要影响.本文描述了事故前人因事件分析的基本程序、方法及分析文档模式,建立了程序化的事故前人因事件分析模式,该分析方法在国内某核电厂最近的HRA分析中得到应用并取得成功. 相似文献
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人因可靠性分析(HRA)已成为概率安全分析(PSA)不可或缺的内容.激发事故初因的人因事件(B类人因事件)分析作为HRA的重要组成部分,在国内外尚无正式的分析报告.本文描述了B类人因事件的定义和分类,建立了B类人因事件分析基本程序和方法,该方法已在国内某核电厂最近的HRA分析中得到应用.文中还对1993年~2002年WANO 940件运行事件和国内某核电厂运行事件进行了B类人因事件统计分析和发生原因分析,并据此提出了预防和减少B类人因事件的措施. 相似文献
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人因可靠性分析(HRA)是概率安全评价(PSA)的重要组成部分。秦山第三核电厂(简称秦山三核)初版HRA由加拿大原子能公司(AECL)完成,其采用的HRA方法为简化的ASEP HRA。为获得更符合秦山三核运行状态实际的HRA结论,本工作对秦山三核重新进行了HRA分析,并增加了事件间的相关性分析。在对国际HRA方法比较研究的基础上,秦山三核HRA采用了规范化的THERP+HCR分析方法。新分析所得数据与AECL数据比较分析结果表明,新分析与AECL的分析判断基本一致,但在合理性和准确性方面较原分析有明显提高,分析结论更符合秦山三核实际。 相似文献
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标准化核电厂人因风险分析(SPAR-H)方法在数字化核电厂的适用性尚未得到充分研究。本研究通过对核电厂数字化后操纵员行为特征的研究和SPAR-H方法在岭东核电厂中的具体应用,分析得出SPAR-H方法应用于数字化核电厂时存在分析结果过度保守、认知过程不够完整、部分行为形成因子(PSF)过于敏感等不足,并针对以上不足对SPAR-H方法提出明确PSF水平的判断标准、完善SPAR-H方法的认知模型、建立人因数据库等改进建议,从而使SPAR-H方法更适用于数字化核电厂的人因可靠性分析。 相似文献
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Atomic Energy - Criteria for optimizing technical solutions in designing and modernizing NPP are considered. Based on their analysis, it is shown that it is economically efficient to increase the... 相似文献
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在设备抗震分析中,设备对基础的作用力是土建设计时所需的重要参数。本文根据不同的工程实例,给出2种设备在地震工况下土建载荷的计算方法,即简便方法和谱分析计算中的刚性区域法,并给出了算例。 相似文献
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The construction and operation of an intense 14-MeV neutron source is essential for the development and eventual qualification of structural materials for a fusion reactor demonstration plant (DEMO). Because of the time required for materials development and the scale-up of materials to commercial production, a decision to build a neutron source should precede engineering design activities for a DEMO by at least 20 years. The characteristic features of 14-MeV neutron damage are summarized including effects related to cascade structure, transmutation production, and dose rate. The importance of a 14-MeV neutron source for addressing fundamental radiation damage issues, alloy development activities, and the development of an engineering database is discussed. For these considerations, the basic requirements and machine parameters are derived. 相似文献
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Michel Laberge 《Journal of Fusion Energy》2009,28(2):179-182
General Fusion is planning to form an FRC or spheromak of 1017 cm−3, 100 eV, 40 cm diameter by merging two spheromaks with reverse or co-helicity. This target will be further compressed in
a 3 m diameter tank filled with liquid PbLi with the plasma in the center. The tank is surrounded with pneumatically powered
impact pistons that will send a convergent shock wave in the liquid to compress the plasma to 1020 cm−3, 10 keV, 4 cm diameter for 7 μs. General Fusion has built a 500 kJ, 80 μs, 6 GW pneumatic impact piston capable of developing
2 GPa (300 kpsi). In this paper we will present the performances achieved to date. 相似文献
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N. S. Babaev A. V. Ochkin Yu. V. Glagolenko E. G. Dzekun S. I. Rovnyi 《Atomic Energy》2003,94(5):306-312
The principles for selecting matrices for immobilizing high-level wastes are examined. It is concluded that actinides should be separated and embeeded in the matrix separately from fission products. The minimum significant specific activity, regulated by NRB-99, cannot be used to estimate the storage time. It is suggested that such values be established as a function of the leach rate of radionuclides and matrix materials from matrices. For this, a standard leaching method using pulverized materials must be specified. Two criteria are proposed for comparing matrix materials. 相似文献
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O. P. Ivanov 《Atomic Energy》2010,108(3):214-222
The software for portable systems for obtaining γ image with coding apertures (masks) is described. The software developed
controls all systems that form an image and obtain shadow patterns, reconstructs the initial γ-image, and processes previously
obtained images. The software is used with portable systems in which URA and MURA type masks with different rank are used
as the coding aperture. Programs for modeling the process of obtaining shadow patterns using real apparatus which has different
positionsensitive detectors are described. Possible configurations of new apparatus which could be of practical interest are
examined. 相似文献
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Bruce A. Buchholz Steven R. Biegalski Scott M. Whitney Scott J. Tumey C. Jordan Weaver 《Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms》2010,268(7-8):773-775
Modeling of nuclear reactor fuel burnup indicates that the production of samarium isotopes can vary significantly with reactor type and fuel cycle. The isotopic concentrations of 146Sm, 149Sm, and 151Sm are potential signatures of fuel reprocessing, if analytical techniques can overcome the inherent challenges of lanthanide chemistry, isobaric interferences, and mass/charge interferences. We review the current limitations in measurement of the target samarium isotopes and describe potential approaches for developing Sm-AMS. AMS sample form and preparation chemistry will be discussed as well as possible spectrometer operating conditions. 相似文献