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裂变核全套中子数据评价     裂变核  中子  评价  截面  核数据       2010/2/26
裂变核全套中子评价数据对反应堆设计和安全运行、乏燃料少锕系核素嬗变率、嬗变系统及高燃耗反应堆设计提供重要的基础数据。文章对核数据分类、现行主要全套评价数据库及全套核数据评价方法进行阐述,并对234U(n,f)和237Np(n,2n)反应截面的实验数据进行评价。完成的裂变核全套中子数据整体满足用户需求,比原评价结果有较明显改进。
针对球床模块式高温气冷堆(HTRPM)燃耗测量系统的设计特点,利用MonteCarlo模拟方法,分析球形体源测量中不同形式的限制束流的准直器的性能及其对燃耗测量的影响。结果表明,对HTRPM在线燃耗测量,选择双锥孔准直器更为适宜。
根据中国实验快堆缓发中子探测系统的结构特点和探测原理,构建了缓发中子探测系统的计算模型。基于该模型,开发了计算机模拟程序。针对不同工况和不同燃料元件包壳破损时刻,进行了缓发中子探测信号的模拟计算。计算结果基本反映了计算情况下缓发中子探测信号的发展趋势。同时,还对燃料温度和燃料燃耗对缓发中子探测信号的影响进行了物理分析。
讨论了判断持续裂变链引发的理论依据,利用基于Geant4toolkit开发的蒙特卡罗直接模拟程序,计算了一系列测试几何和超瞬发临界5c/的GodivaⅠ反应堆内持续裂变链的引发概率。结果表明,蒙特卡罗直接模拟计算的结果与Mercury程序及确定性理论结果均一致
In the framework of the environmental impact studies of the nuclear research reactor of Algiers, we will present the work related to the atmospheric dispersion of releases due to the installation in n...
The evaluation of uncertainty constitutes the necessary supplement of best-estimate calculations performed to understand accident scenarios in water-cooled nuclear reactors. The needs come from the im...
The horizontal coolant channel is one of the important parts of primary heat transport system in PHWR type of reactors. There are in all 392 channels in the core of Indian 540 MWe reactor. Each ...
The Ignalina nuclear power plant is a twin unit with two RBMK-1500, graphite moderated, boiling water, multichannel reactors. After the decision was made to decommission the Ignalina NPP, Unit 1 was s...
The main challenge in nuclear fuel cycle closure is the reduction of the potential radiotoxicity, or of the time in which that possible hazard really exists. Probably, the transmutation of minor actin...
This paper presents investigations on the possible combination of modular high-temperature gas-cooled reactor (MHTGR) technology with the supercritical (SC) steam turbine technology and the prospectiv...
The development of a conceptual design of an industrial-scale transmutation facility (EFIT) of several 100 MW thermal power based on accelerator-driven system (ADS) is addressed in the frame of ...
In this work, we report on Euler-Euler large eddy simulation (EELES) of dispersed bubbly flow in a square cross-sectional bubble column. Simulations are performed using the Neptune_CFD package, and re...
The NURESIM Project of the 6th European Framework Program initiated the development of a new-generation common European Standard Software Platform for nuclear reactor simulation. The thermal-hydraulic...
This paper describes the modeling of boiling multisize bubbly flows and its application to the simulation of the DEBORA experiment. We follow the method proposed originally by Kamp, assuming a given m...
Computational fluid dynamics (CFD) codes are widely used in industrial applications for single-phase flows (e.g., in the automotive or aircraft industries). On the other hand, the application of CFD f...

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