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一体化堆顶结构对核反应堆中控制棒驱动机构(CRDM)的线圈组件通风冷却有重要作用。本文对华龙一号反应堆的一体化堆顶通风结构建立三维模型,运用ANSYS CFX模拟研究了在不同通风量下通风结构—CRDM线圈组件之间的气流速度和压降分布情况。为了验证数值模拟方法的正确性,建立1:1通风结构试验装置,在7×10~4、8×10~4、9×10~4和10×10~4m~3/h风量下进行冷态试验研究,试验结果与模拟结果吻合良好,验证了该模拟方法的正确性。考虑流体的对流传热,在控制棒驱动机构有热源的情况下模拟一体化堆顶结构的通风冷却性能。结果表明,一体化堆顶结构能很好地满足反应堆堆顶通风冷却的要求。 相似文献
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[英国《国际核工程》1996年7月号第32页报道] 加拿大原子能有限公司(AECL)正在把注意力集中在提高CANDU型堆的经济性、安全性和核燃料循环灵活性上,以此来占据全球的核市场。 在CANDU 9型堆的开发中,保留了CANDU型堆的全部被证实的特点:不停堆换料;燃料循环灵活性;重水慢化剂;以及简单、低价的天然铀燃料棒束。此外,还不断地对CANDU型堆进行改进,以满足世界市场不断增长的需求。这些改进不仅用于先 相似文献
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本文从控制棒驱动机构通风冷却论述开始,重点介绍了反应堆顶部驱动机构常温通风均匀性试验研究中应注意的一些问题,如风罩围板的选用、风管的安装位置、静压箱容积的考虑等。并通过送、吸风两类工况的试验数据比较及原理上的分析,给人以有益的启迪。 相似文献
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四、拉丁美洲阿根廷削减核计划预算,但不会影响698MWe 的阿图查2号堆建造。阿根廷对发展小型核反应堆感兴趣,并倾向于引进加拿大的 CANDU 型堆。阿原则上同意购买一座600MWe CANDU 型堆。 相似文献
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【欧洲核学会《核新闻网》1992年12月1日报道】在莫斯科最近一次新闻发布会上,俄罗斯原子能部首次透露了有关该国乏燃料管理、后处理和贮存的新消息。据透露,俄罗斯已经例行后处理来自VVER-440型堆的乏燃料。为了后处理VVER-1000型堆的乏燃料,一个新的后处理厂正在建造中。对 相似文献
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堆顶固定屏蔽在中国实验快堆(CEFR)中承担着重要功能,对其进行充分冷却极其重要。本文采用CFD方法对该设备的冷却系统进行了三维数值研究,详细分析了该冷却系统的流动特性和水力学设计,并对设计中的不足提出了优化建议。研究表明,该冷却系统基本可满足要求,但部分环节需要优化。将调节阀尽量均匀布置可改善水平风道流场分布;入口处设置两道通风孔可提高竖直风道内空气流动的均匀性;调节阀开度应适当增加以进一步满足流量分配需求。该研究可为CEFR运行安全和类似冷却系统的设计提供参考。 相似文献
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【英国《国际核工程》1991年6月号第52页报道】自瑞典 ABB 原子能公司开始进行 PIUS 型堆的设计工作以来,差不多已有10个年头了。开发这种堆的目的在于改进轻水堆的安全性,使之具有固有安全或非能动安全的特点。PIUS 型堆的研究已经有许多年了,但目前的研究工作重点集中在4个环路的 PIUS 型(600 MWe)堆上。 相似文献
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为保证华龙一号堆内构件的结构完整性,在华龙一号首堆(福清核电厂5号机组)热态功能试验期间应对堆内构件的流致振动行为迚行现场实堆测量,幵且需对现场实堆测量中涉及的实测测点布置迚行论证分析。本文将华龙一号堆内构件与M310堆型堆内构件的结构和流场迚行了对比,得出需要布置测点的新结构位置以及相同结构的薄弱位置;通过对华龙一号堆内构件比例模型试验结果的分析,找出流致振动相对薄弱的结构,在实堆上重点布点测量薄弱结构,其余位置在实堆上考虑少量测点迚行验证性测量;对于以上提到的薄弱位置以及考虑到实堆感应器测点失校的可能性,适当地考虑测点的冗余。通过与同类核电厂流致振动测量的比较,结果表明,华龙一号确定的测量结构、测点布置合理,幵且该测点布置斱案已在福清核电厂5号机组实施。 相似文献
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陆双桐 《核电子学与探测技术》1983,(5)
本文介绍了BZD-4型堆用圆筒形电极补偿硼膜中子电离室的工作原理和性能参数。给出了典型的测试数据,并与BZD-2型平板形电极电离室进行了对比。 相似文献
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日本文殊原型快堆堆芯出口腔室热分层现象数值模拟 总被引:1,自引:1,他引:0
本文利用商业CFD程序STAR-CCM+,采用合理的网格生成技术及物理模型,对日本文殊原型快堆堆芯出口腔室建立近似1∶1的模型,模拟分析40%额定功率停堆过程中堆芯出口腔室的瞬态工况,获得腔室内较为完整的热分层进程。结果表明:停堆2 min后腔室内出现稳定热分层现象;10~21 min时热分层通过上升桶桶顶位置;10~140 min热分层处于上升筒顶端位置附近期间,腔室内流型不稳定;140 min后热分层完全处于上升桶顶,桶内流型稳定且接近于停堆前。模拟结果与实验数据对比表明,停堆初期4 min内两者符合较好,表明本文模拟方法适用于停堆工况堆芯出口腔室热分层进程模拟;之后模拟进程明显快于实验,分析其偏差主要来自模拟边界及结构与实际的差异。 相似文献
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A hypothetical core disruptive accident in a liquid metal fast breeder reactor (LMFBR) results from the interaction between molten fuel and liquid sodium, which creates a high-pressure bubble of gas in the core. The violent expansion of this bubble loads and deforms the vessel and the internal structures. The MARS experimental test simulates a HCDA in a small-scale mock-up containing all the significant internal components of a fast breeder reactor. The mock-up is filled with water, topped by an argon blanket, and the explosion is generated by an explosive charge.This paper presents a numerical simulation of the test with the EUROPLEXUS code. The top closure is represented by massive structures and the main internal structures are described by shells. The current numerical results are described and compared with the experimental ones, and previous computations with the CASTEM-PLEXUS code. 相似文献
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计算了西安脉冲堆发生失水事故后,堆芯发射的γ射拇因失去堆水池屏蔽层,直接穿透空气被顶部天花板反散射后在堆水澉平台产生的辐射剂量率。计算结果与TRIGA-2堆结果相符合,是确定事故后工作人员在平台可停留时间的基础,同时为适当地制定事故处理措施提供了参考。 相似文献
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C-ring is the core part for seal of the reactor pressure vessel top cover and cylinder, and the sealing performance is directly related to the safety and stably operation of the nuclear power plant. For a long time, the manufacturing technology of C-ring was monopolized by foreign company, with high price and long supply cycle. It is verified that the C-ring made in China fulfill the commercial application, through sealing properties test, helium leak detection test, water pressure test and thermal-cold cycle test. The functional impact analysis proved the equivalence of the domesticated C-ring. The installation quality of domestic C-ring was strictly controlled in nuclear power plant, and the performance of the domestic C-ring was verified by the in-service hydraulic test and the running test. 相似文献
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The high temperature engineering test reactor (HTTR) is the first high-temperature gas-cooled reactor in Japan with reactor outlet gas temperature of 950 °C and thermal power of 30 MW. Sixteen pairs of control rods are employed for controlling the reactivity change of the HTTR. Each standpipe for a pair of the control rods, which is placed on the top head dome of the reactor pressure vessel, contains one control rod drive mechanism. The control rod drive mechanism may malfunction because of reduction of the electrical insulation of the electromagnetic clutch when the temperature exceeds 180 °C. Because 31 standpipes stand close together in the standpipe room, 16 standpipes for the control rods, which are located at the center, should be cooled effectively. Therefore, the control rod drives are cooled indirectly by forced air circulation through a pair of ring-ducts with proper air outlet nozzles and inlets. Based on analytical results, a pair of the ring-ducts was installed as one of structures in the standpipe room. Evaluation results through the rise-to-power test of the HTTR showed that temperatures of the electromagnetic clutch and the ambient helium gas inside the control rod standpipe should be below the limits of 180 and 75 °C, respectively, at full power operation and at the scram from the operation. 相似文献
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Masaki Inoue Kazuya Yamamoto Takashi Sekine Masahiko Osaka Naoya Kushida Takeo Asaga 《Journal of Nuclear Materials》2003,323(1):108-122
Power-to-melts of uranium-plutonium oxide fuel pins at an initial startup condition were experimentally obtained from the B5D-2 test in the experimental fast reactor JOYO in Oarai Engineering Center. MCNP code calculations were combined with burnup measurements to determine linear heat rating of the test fuel pins. To identify the axial incipient melting positions corresponding to the power-to-melts, solidified grain morphology and molten fuel axial movements were characterized. Extensive observations on longitudinal ceramographs allowed classifying molten fuel settlements near bottom and top extents of axial fuel melting into three types. The power-to-melts depended slightly on fuel-to-cladding gap sizes and clearly on both oxygen-to-metal ratios and densities of fuel pellets. These dependencies resulted from the fuel pellet cracking and relocation behavior, which fairly improves heat transfers across the gaps. Also, the power-to-melt at the bottom position was higher than that at the top position due to an axial gradient of cladding temperatures in each fuel pin. 相似文献