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脉冲棒驱动机构是脉冲堆上的一个关键性运动设备,是该堆在脉冲运行时的执行机构,稳态运行时可兼有补偿棒的运行职能。该机构采用气-电联合驱动。本文就该机构的设计原理、结构特点、运动操作及主要参数的计算作了扼要的介绍,还就产品样机的试验结果进行了说明。 相似文献
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西安脉冲堆稳态控制棒驱动机构是实现反应堆启动、功率调节和停堆的关键设备。该机构采用滚珠丝杠副的传动方式,通过电磁铁的吸合,可以带动稳态控制棒上下运行,当释放电磁铁时,可以实现快速落棒。本文介绍了稳态控制棒驱动机构的结构特点、设计参数和试验情况。该机构已成功应用于西安脉冲堆。 相似文献
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西安脉冲堆脉冲控制棒驱动机构是实现反应堆脉冲运行的关键设备。该机构采用滚珠丝杠副的传动方式,通过气压缸实现控制棒的脉冲发射。脉冲控制棒驱动机构具有全行程脉冲时间短、结构简单、维修方便的特点。试验表明:脉冲控制棒驱动机构最大负荷大于300N,全行程脉冲时间小于100ms,落棒时间小于1.2s,寿命大于4000次脉冲发射运行,平均无故障时间大于400次脉冲发现运行。该机构已成功应用于西安脉冲堆。 相似文献
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我国第一座脉冲反应堆 总被引:4,自引:3,他引:1
我国第一座脉冲反应堆是座小型池式研究堆,采用铀氢锆(UZrH_(1.6))燃料-慢化剂粗棒元件。堆芯靠轻水自然循环冷却,石墨作反射层。该堆具有很大的瞬发负温度系数,不仅能稳态运行,而且还能进行独特的脉冲运行和方波运行。稳态运行额定功率1000kW,堆芯平均热中子通量1.4×10~(13)n/(cm~2·s),当引入3元(2.1×10~(-2)△K/K)瞬发正反应性脉冲运行时,峰功率约为3420MW,中子通量峰值约为6×10(16n)/(cm~2·s)。固有安全、经济及多功能是该堆型最显著的特点。本堆已于1990年7月22日达到首次临界,尔后开始试运行。 相似文献
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本文采用RMC模拟计算了西安脉冲堆(XAPR)稳态堆芯第1循环燃料元件的精细燃耗分布情况,根据XAPR运行温度制备了多温度点氢化锆的热化截面,计算了零燃耗下XAPR冷态和热态实验的keff。分别考虑燃料棒径向和轴向空间离散化下温度反馈的结果,确定了首循环脉冲堆三维燃耗最深的位置。结果表明,采用燃料棒径向燃耗分区的15 EFPD下D5和G14燃料棒燃耗计算结果较径向不分区的结果更接近实验值,RMC应用于XAPR精细燃耗计算具有较高可靠性,可用于脉冲堆物理计算与安全分析工作。 相似文献
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本文简要地介绍了我国第一座脉冲堆稳态运行试验方法和设施,给出了冷态和热态以及不同功率下的临界棒位,并给出了反应性、中子通量、功率系数、平衡氙毒和碘坑的测量结果,提供了一批有价值的工程试验数据。本堆实现了1MW 稳态功率运行,进行了连续72小时满功率运行,对反应堆的控制、保护、测量仪器及各系统和设备进行了考验。试运行结果表明:本堆性能良好,各项指标均已达到了设计要求。 相似文献
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本文通过点堆模型,分析了脉冲堆瞬态棒提升速度对于脉冲运行工况的影响。得到如下结论:1.瞬态棒出堆的末速度对功率脉冲的峰值影响最大。2.出堆速度越高,投入的过剩反应性的损失越小。3.存在一个临界速度,当低于该速度时,反应堆将不会产生脉冲功率。以这一分析为基础,我们选用快排型气缸作为瞬态棒的提升机构。在对气缸的运动进行分析计算及试验的基础上,提出了设计曲线及设计方法。在这一试验中,气缸的末速度达到11m/s。 相似文献
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脉冲堆驱动线结构大多为细柔部件,且对其传动功能的要求较高。因此,首先将堆桥及整个驱动线作为一个完整的力学模型进行分析,其次分析各个子结构。并将计算结果与实验结果作了比较,表明分析的结果是可靠的,证明子结构法是一种简便实用、行之有效的分析方法。最后用响应谱法的结果对关键部位作出了初步地震安全评价。 相似文献
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《Journal of Nuclear Science and Technology》2013,50(3):226-238
The NSRR programme is in progress in JAERI using a pulsed reactor to investigate fuel behaviors under the reactivity-initiated accident conditions. Pulsing characteristics and experimental capability, especially heat deposition in test fuel rods given by a single pulse are key parameters to this purpose. In pulsing performance tests, it has been ascertained that the maximum pulsing with 4.67$ (=3.41%δk) brings peak reactor power of 21,100 MW and core energy release of 117 MW·sec. The calculated time responses of reactor power, fuel temperature and cladding surface temperature as well as these maximum values at various pulse sizes agreed well with measured data. In addition, it has been also ascertained by measurement as well as analysis that there are no essential differences in pulsing characteristics between the pulsing from critical and that from subcritical. The heat deposition in a test fuel rod given by a single pulse is much enough as predicted, and a 2.6% enriched BWR type fuel rod gains about 230cal/g-UO2 in the maximum pulsing. In case of irradiation of clustered five test fuel rods by a single pulse, heat deposition reduces by about 20% for a surrounding rod and about 40% for a center rod in comparison with that in a single rod irradiation. 相似文献
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为了给在建中的西安脉冲堆数字化仪表与控制系统提供调试用模拟信号源、验证功率调节方法以及人员培训等,研制了一套西安脉冲反应堆半实物仿真系统。提出了半实物仿真系统的设计思想,设计了系统框架。改进了堆芯仿真物理模型,使用MATLAB编制了堆芯实时仿真程序。采用组态王软件编制了人机界面,采用可编程控制器S7-200进行棒位控制和棒位测量。研制了控制棒驱动机构模拟件、信号发生器和手动操作盘等多个硬件设备,建立了系统内部的通讯。在该半实物仿真系统上模拟了升、降控制棒的功率变化和发射脉冲后的脉冲参数,与堆上实验结果符合较好,测量了信号发生器的输出信号,与预期一致。结果表明,该半实物仿真系统能够实现设计目的且性能良好。 相似文献
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控制棒驱动机构是反应堆控制和保护系统的伺服机构,是执行反应堆功率调节、紧急停堆的重要核安全设备。控制棒驱动机构成本较高,如何合理确定其备件数量对于提高反应堆的可运行性具有重要意义。本文针对控制棒驱动机构,在系统连续运转时间不小于换料周期的约束条件下,提出了一种确定控制棒驱动机构备件数量的优化方法--分组备件数量优化方法,给出了总费用最少的各子系统的备件配置方案。通过随机模拟计算对分组备件数量优化方法与常规算法进行比较,结果表明:该方法常优于常规算法,在保证控制棒驱动机构可用性的前提下,优化备件数量配置可降低成本。该优化方法同样适用于其他设备的备件分析,对工程中设备备件的分析与研究具有指导意义。 相似文献
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《Journal of Nuclear Science and Technology》2013,50(2):69-74
The Doppler limited power excursion characteristics of a light water reactor and the shutdown mechanism by scram were analyzed on the Hitachi Training Reactor (HTR). For the purpose of the pulse operation tests, modifications were applied to the HTR to provide pulsing capability; a pulse rod was added, together with a back up device for shutdown, and provision of three instrumented fuel assemblies, equipped with thermocouples; the Al-clad fuel rods were replaced by stainless steel clad rods. About 100 runs of pulse operation tests were performed in fullest security with reactivity insertions ranging up to 1.0 % Δk/k, in which last case the peak power reached 38 MW, with a reactor period of 29 msec. 相似文献
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A 200 MW nuclear heating reactor (NHR) was developed based on the 5 MW testing heating reactor (THR-5). In order to improve its features, the INET was used to optimize its structure design. One task was to design the upper hydraulic drive control rod, which is located at the upper part of the reactor core, so that the fuel rod in each corner of the bundle will not be removed as they are in the THR-5. A program based on the method of characteristics was run to investigate the dynamic behavior of the upper hydraulic control rod drive system. The steady-state and dynamic characteristics of the control rod were studied. The influence of the reactor temperature and structure parameters on the operation reliability was investigated. Finally the optimal design parameters of the upper hydraulic drive control rod were obtained. 相似文献
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本文介绍了在脉冲堆零功率物理实验中,利用硼中毒法测量反应性的原理和方法,给出了脉冲堆堆芯的硼微分价值、控制棒效率和总后备反应性的实验结果。还利用硼中毒法和脉冲中子源法配合进行脉冲堆控制棒之间反应性干涉效应的实验研究,取得了初步结果。 相似文献
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介绍了我国自主研制的第一套商用脉冲反应堆脉冲参数测量装置(西安脉冲堆脉冲参数测量装置)的设计方案、系统组成、工作原理、技术特点和应用情况。该装置是西安脉冲反应堆主控室控制台的主要仪表之一,具有脉冲参数测量和堆保护功能。装置采用微电子和计算机技术,实现了对反应堆脉冲工况下堆功率变化、脉冲波形与多个参数的实时自动测量与显示,并在功率超限时向反应堆保护系统和报警系统发出信号。文中对装置的工作特性做了描述,并对现场调试和运行情况作了简要介绍。 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