共查询到18条相似文献,搜索用时 46 毫秒
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An intelligent on-line monitoring device for fuel cladding defect has been developed. HPGe with anti-Compton scattering detection system is used to measure the activity of characteristic radionuclides in primary cooling water, and the multi-nuclide group coupled analysis method is used to diagnose the defect of the fuel cladding. The verification and calibration test shows that the absolute relative standard deviations of the measured typical nuclides 57Co, 137 Cs and 60Co are less than 3%, and the minimum detectable activity can reach 6.5 Bq. 相似文献
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邓浚献 《核工程研究与设计》2006,(1):14-19
本文简介反应堆破损燃料元件的监测、定位和处理;反应堆运行时的监测与定位;换料时或换料后的监测;在燃料组件内鉴别破损的燃料棒;破损燃料棒拆出后的监测与定位;燃料组件的监测、拆卸和修复等方面在国际上的研究开发现状。 相似文献
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从反应堆运行工况及材料因素,讨论了水堆燃料元件包壳的水侧腐蚀问题。为满足高性能燃料元件的要求,包壳的水侧腐蚀性能需要改善。本文根据最近的一些研究结果,讨论了各种可能有效的措施。 相似文献
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法国压水堆燃料元件新一代包壳材料的发展 总被引:4,自引:1,他引:3
概述了法国对核电站燃料元件包壳材料锆合金的开发与研究现状,着重介绍了所开发的新锆合金(M2,M3,M4,M5合金)在堆内外的性能。其中M4和M5合金包过央燃料棒燃耗达到55GW.d.t^-1的辐照考验结果表明,它们的堆内的腐蚀,蠕变和辐照伸长等性能优于改进型Zr-4合金包壳。 相似文献
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为提升对核反应堆燃料棒包壳破损的预测能力,建立两个串联的人工神经网络分别判断燃料棒包壳是否破损以及破损程度。通过改变沾污铀质量、增加数据扰动、改变运行功率和使用更少的特征核素进行训练,对用于判断是否破损的神经网络模型和判断破损等级的神经网络进行了性能测试和分析。在沾污铀质量小于0.5 g、数据扰动在30%以内、单棒功率在77 kW到120 kW之间的条件下,第1个人工神经网络能较好地判断出是否破损。第2个神经网络,对于考虑的5种破损程度,判断的精确性较高。与传统的碘同位素比值法相比,神经网络方法响应更快,精度更高。结果表明,人工神经网络可用于预测反应堆燃料包壳是否发生破损以及破损程度。 相似文献
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水化学对燃料元件包壳腐蚀行为的影响 总被引:2,自引:0,他引:2
燃料元件包壳的水侧腐和吸氢是当前进一步提高燃耗的主要限制因素,由于一回路水中加入H3BO3和LiOH,使包壳的腐蚀问题变得更为复杂。本文综述了LiOH及LiOH-H3BO3对锆合金水侧腐蚀的影响,以及研究这种影响机理的现状。 相似文献
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基于COMSOL平台开发了一套基于多物理场全耦合的燃料性能分析程序,并通过径向功率分布模型对比验证了该程序的正确性与准确性;然后进一步分析了U3Si2燃料与双层SiC包壳组合、U3Si2燃料与锆合金包壳组合在反应堆正常运行工况下的性能,并与UO2燃料与锆合金的组合进行了对比分析。计算结果发现U3Si2燃料与锆合金包壳组合相比UO2燃料与锆合金的组合具有更低的燃料中心温度、裂变气体释放量及内压,但气隙闭合时间会提前;而U3Si2燃料与双层SiC包壳的组合相比U3Si2燃料与锆合金的组合具有更高的燃料中心温度、更大的裂变气体释放量及内压,且随着燃耗的增加,其燃料中心温度大幅增加,与锆合金包壳相比,双层SiC包壳能够有效延迟气隙闭合,缓解燃料与包壳的力学相互作用。 相似文献
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《Journal of Nuclear Science and Technology》2013,50(9):1074-1079
A correlation for RIA fuel failure threshold has been derived and compared with recent experimental data. The correlation can be used for UO2 and MOX fuel and at hot zero power and cold zero power transients, account taken for the different initial enthalpy and for the lower ductility at cold conditions. It can also be used for non-zero power transients, provided that a term accounting for the start-up power is incorporated. A probabilistic approach has been attempted for the cold zero power case. For LOCA, a correlation has been derived expressing the LOCA limit as a function of the hydrogen accumulated in the cladding during base irradiation. However, LOCA experimental data exhibit a significant scatter, possibly because results depend on details in the conduct of the tests. Consequently, predictions of LOCA limits vs. burn-up are affected by appreciable uncertainty, and more data derived from testing of high burn-up cladding specimens are needed in order to reach firm conclusions. 相似文献
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《Journal of Nuclear Science and Technology》2013,50(6):892-901
The cladding failure analyses on various beam transients of Lead-Bismuth-cooled Accelerator-Driven System (ADS) were performed with ADSE code and the cladding failure analysis program. First, the cladding failure analysis program was developed. This program is intended for creep ruptures analysis using ADSE code and employs the method of Cumulative creep Damage Fraction (CDF) calculation. Beam diameter expansion, beam flattening, beam hollowing, and beam incident position change were analyzed for the ADS model proposed by JAEA. As a result, beam diameter expansion, beam flattening, and beam hollowing would not lead to cladding failures but beam incident position change was revealed to have a high risk for the cladding failures. Some core designs were proposed for the prevention of failure. The changes of sizes such as plenum length were not effective for CDF reductions. The application of SUS316FR steel cladding instead of Mod.9Cr-1Mo steel showed good performance but the application of SUS316FR steel needs some provisions for erosions and corrosions. The fuel composition change was very effective for CDF control and this measure would be the best modification for the prevention of cladding failures. 相似文献
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《Journal of Nuclear Science and Technology》2013,50(9):1128-1135
Among a series of power ramp tests on 25 Zr-lined segment rods of burnup ranging from 43 to 61 GWd/t, five segment rods failed during the power ramp tests. One segment rod irradiated for 3 cycles (43 GWd/t) failed with a pinhole due to PCI/SCC. The rest of higher burnups failed with an axial crack on the outer surface. The failure threshold power tended to decrease as burnup increases. Post irradiation examinations revealed increased cladding hydrogen absorption and its precipitates in the cladding outer rim after 4 and 5 cycle irradiations, in contrast to a uniform hydride distribution and a small hydrogen content after 3 cycle irradiation. Metallographic observations suggested an axial crack failure mode induced by the combined effects of high stress and hydrides precipitated in a radial direction during power ramp. The axial crack failure during the power ramp is supposed to be initiated by a cracking of radial hydride formed by hydride re-distribution and re-orientation at the cladding outer rim and to propagate through a process of hydride concentration and precipitation at the crack tip. Research programs of experimental and analytical studies to clarify the conditions of such mechanism are on-going focusing on the hydrogen behavior and mechanical performance of the irradiated cladding. 相似文献
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燃料棒包壳辐照蠕变与生长行为模拟研究 总被引:1,自引:0,他引:1
根据建立的包壳材料和行为模型,利用ABAQUS对包壳辐照蠕变与生长行为进行相关模拟研究。在设定的稳态工况下,计算了包壳的辐照蠕变,分析了它的应力以及蠕变的关系。通过设置节点集和不同路径方式,分析了包壳的辐照生长现象,表明了ABAQUS在核燃料性能研究方面的适用性。以及利用ABAQUS的二次开发接口,可以把自定义的模型结合到商用的有限元软件中,利用商用有限元软件的优势,快速解决部分核燃料模拟中的问题。 相似文献