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Lingzhi Xia Manir U. Isham Vladimir Ponomarev 《Journal of Nuclear Science and Technology》2016,53(10):1513-1520
Performance of a recently developed signal processing system for CANDU (Canada Deuterium Uraniu) reactor shutdown system 1 (SDS1) is evaluated in this paper. The evaluation is carried out in MATLAB/Simulink software environment as well as with an existing power measurement and signal processing system. The new signal processing algorithm is obtained based on the synthesis of several first order low pass filters with different delayed time constants. Throughout this paper, a special attention has been paid to compare the new signal processing system with the existing one. The dynamic behavior of the new signal processing system in the practical large loss of coolant accidents (LLOCA) events has also been examined. Simulation results show that during the LLOCA event, the reactor trip time, as well as the peak power, is decreased remarkably. Through the simulation studies, it has convincingly demonstrated that the new signal processing system has significant advantages over the existing system in terms of the improved trip response and accommodation of the spurious trip immunity. This advantage will significantly enhance the safety margin, or will bring economical benefits to nuclear power plants. 相似文献
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介绍了在总承包商交钥匙合同模式下,业主在进口设备质量监督方面所开展的工作,以及从中得到的经验教训。 相似文献
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An investigation on recycling the recovered uranium from electro-refining process in a CANDU reactor
Feasibility studies for recycling the recovered uranium from electro-refining process of pyroprocessing into a Canada Deuterium Uranium (CANDU) reactor have been carried out with a source term analysis code ORIGEN-S, a reactor lattice analysis code WIMS-AECL, and a Monte Carlo analysis code MCNPX. The uranium metal can be recovered in a solid cathode during an electro-refining process and has a form of a dendrite phase with about 99.99% expecting recovery purity. Considering some impurities of transuranic (TRU) elements and fission products in the recovered uranium, sensitivity calculations were also performed for the compositions of impurities. For a typical spent PWR fuel of 3.0 wt.% of uranium enrichment, 30 GWD/tU burnup and 10 years cooling, the recovered uranium exhibited an extended burnup up to 14 GWD/tU. And among the several safety parameters, the void reactivity at the equilibrium state was estimated 15 mk. Additionally, a simple sphere model was constructed to analyze surface dose rates with the Monte Carlo calculations. It was found that the recovered uranium from the spent PWR fuel by electro-refining process has a significant radioactivity depending on the impurities such as fission products. 相似文献
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针对CANFLEX组件装载MOX燃料在CANDU重水堆中的应用进行了时均和瞬态验证计算。计算结果表明,最大通道功率和最大棒束功率均未超过限值。勿需对堆芯结构和运行模式做重大改变即可完成从天然铀堆芯向MOX堆芯的过渡。提出了应用MOX燃料的PWR/CANDU联合燃料循环策略。估算表明,秦山三期CANDU堆采用先进PWR/CANDU联合燃料循环,将使燃耗提高到13900MW·d/t(U);相对于PWR和CANDU堆各自独立的燃料循环,每年节省天然铀资源180t,减少乏燃料处置量约128t。 相似文献
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简单概括了AECL为秦山CANDU 6所作的放射性源项研究 ,回顾了TQNPC为主体的审评对该项工作的作用和影响 ,同时提出若干改进建议 相似文献
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核反应不停堆换 可避免要采用比较复杂和精致的技术,这种系统必须是可靠 掀料操作必须遥控进行。本文简要介绍了秦山三期CANDU核电厂燃料操作系统,以及不停堆换料,乏燃料运输等情况。 相似文献
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研制了非线性迭代半解析节块法的扩散程序和稳态单通道热工水力程序,并将二者联接形成了CANDU重水堆燃料管理软件包FMPHWR,实现了物理与热工水力的耦合,参考压水堆(PWR)的经验,提出了类似PWR的考虑局部参数变化的参数化截面方法。对原有的时均计算模型进行了修正,提出了考虑热工水力反馈的时均计算模型,通过数值计算表明:FMPHWR具有更高的计算精度。 相似文献
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