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运用机械可靠性理论,利用力学仿真分析高温气冷堆示范工程——球床模块式高温气冷堆核电站(HTR-PM)控制棒组件的受力情况和薄弱区,识别出其薄弱区位于控制棒组件连接头位置;基于概率断裂力学的可靠度-寿命计算方法,结合辐照对疲劳寿命模型的影响,并考虑所受应力情况,建立可靠度-寿命模型,计算HTR-PM控制棒组件在辐照减弱系数为0.7时的可靠度-寿命。计算结果表明,可靠度水平为0.99时,HTR-PM控制棒组件寿命约为15万次动作循环,辐照对控制棒组件寿命影响较大。本研究可为HTR-PM控制棒组件设备可靠性管理提供参考。 相似文献
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《核电子学与探测技术》2015,(6)
事故情况下控制棒组件会在自身重力作用下下落,下落时间是衡量核电站安全运行的重要参数之一。通过建立落棒物理模型,分析落棒的物理过程以及控制棒下落过程中的各阶段的受力情况,得到了落棒控制方程。采用VS2010软件对控制方程数值求解,完成了控制棒组件竖直及倾斜下落过程的时程的分析,对比了倾斜落棒角度对落棒时程的影响,得出最大倾斜落棒角度,为反应堆控制棒组件的设计提供依据。 相似文献
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为验证超临界压水堆改进型控制棒组件能否实现预期水力缓冲功能,采用计算流体力学分析软件Fluent、基于6自由度(6DOF)模型的铺层法动网格技术,对其落棒过程进行研究,分析了控制棒组件落棒时间和落棒末速度。结果表明:相比改进前的设计,改进型控制棒组件落棒时间虽有所增大,但仍然能满足安全要求;落棒末速度大幅下降,落棒冲击力降低,从而能够保证控制棒组件及燃料组件的结构完整性。改进型控制棒组件的设计能够实现预期的水力缓冲功能,可用于超临界压水堆堆芯设计。 相似文献
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sm-TMSR是中国科学院钍基熔盐堆核能系统中心(TMSR)设计的一款小型模块化多用途钍基熔盐示范堆。本文就sm-TMSR堆芯的控制棒布置进行了物理分析。首先,对熔盐堆特有的反应性变化现象进行了分析,提出了sm-TMSR控制棒的功能和需求,即:对于调节棒,要求设计的总价值在寿期初等于或略大于2.5×10-2,寿期末等于或略大于2.06×10-2;对于停堆棒,考虑卡棒准则,要求设计的单根棒价值在寿期初大于等于2.1×10-2;其次,计算了不同位置、不同控制棒孔道直径以及有无哈氏合金套管的单根控制棒价值;最后根据控制棒价值的需求大小,确定了控制棒组件在堆芯较为优化的物理设计:①控制棒组件孔道直径为9?cm,无哈氏合金套管;②4根控制棒成“十”字形分布,2根停堆棒均匀布置在堆芯的第1圈,2根调节棒均匀布置在堆芯的第6圈位置。 相似文献
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堆芯中核燃料发生裂变时,伴随产生极强的中子及γ辐射,这些辐射在燃料组件中发生能量沉积,产生热应力、辐照损伤等诸多影响反应堆安全运行的因素.尤其对于新型含钆可燃毒物棒组件,国内对此方面的研究需要进一步开展.采用三维蒙特卡罗输运计算程序MCNP和基于ENDF/B的连续截面数据库,对压水堆18个月长、短周期装料方式的堆芯相关组件内热源的释热率分布进行详细计算,计算得出控制棒、阻力塞棒和新型含钆可燃毒物棒释热率精确计算值,并对不同版本数据库中部分关键核素截面对计算结果的影响进行比较分析,为核反应堆堆芯设计提供参考. 相似文献
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《Journal of Nuclear Science and Technology》2013,50(2):108-116
A method of optimizing fuel assembly allocation is proposed for a certain type of refueling schedule problem of Boiling Water Reactor (BWR) in which cycle length and number of fresh fuel assemblies to be loaded are predetermined The optimization is aimed at minimizing power peaking factor. The problem is decomposed into two subproblems: one to optimize the global region-wise shuffling scheme and the other to optimize assembly allocation. Linear programming is iteratively solved in the former subproblem such that the maximum excess reactivity is minimized and a direct search method is used in the latter subproblem The method is successfully applied to the 2nd and the 3rd cycle refueling schedule problems of a 460 MWe BWR. The optimized reloading patterns are compared with other non-optimal patterns which have much simpler or more symmetrical shuffling schemes. The optimization shows merit in reducing power peaking without sacrificing the cycle length. 相似文献
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This paper presents the study of load follow operations without boron adjustment for CPR1000. To enable the CPR1000 to perform load follow maneuvers without changing soluble boron concentration, the worth of Rod Cluster Control Assemblies (RCCAs) are reconfigured with their amount and location unchanged according to the reactivity variations during the load follow transient. To ensure the real-time ability of the reactor core, the target axial offset (AO) during load follow operations is set to the same value with that in based load, and the Delta-I is maintained within the special trapezoidal shaped target band around its target value.For the simulation of the reactor core, the time-dependent one-dimensional two group diffusion equations with the reactivity feedback of moderator temperature, Doppler and xenon–iodine are used. The transverse buckling is adjusted at each time interval so that the one-dimensional model can match the average characteristics of the three-dimensional reactor core accurately. To show the superiority of the improved core control strategy for CPR1000 reactor, the load follow results employing the purposed boron-adjustment free control strategy are compared to those obtained with the typical MODE-G control strategy. It has been demonstrated by the simulation results that the load follow capability of CPR1000 reactor is greatly improved due to the elimination of boron concentration adjustments during load change transients. Full load follow capability of the reactor has been extended from the initial 80% of cycle life to more than 90% of cycle life. Thus, the boron adjustment free improvement on the MODE-G core control strategy is feasible for CPR1000, which can improve the economical performance of the plant and simplify the operational process during power maneuvers. 相似文献
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Correct communication between main control room (MCR) operators is an important factor in the management of emergency situations in nuclear power plants (NPPs). For this reason, a standard communication protocol for the management of emergency situations in NPPs has been developed, with the basic direction of enhancing the safety of NPPs and the standardization of communication protocols. To validate the newly developed standard communication protocol, validation experiments with 10 licensed NPP MCR operator teams was performed. From the validation experiments, it was found that the use of the standard communication protocol required more time, but it can contribute to the enhancement of the safety of NPPs by an operators’ better grasp of the safety-related parameters and a more efficient and clearer communication between NPP operators, while imposing little additional workloads on the NPP MCR operators. The standard communication protocol is expected to be used to train existing NPP MCR operators without much aversion, as well as new operators. 相似文献
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177燃料组件堆芯反应堆通常采用G模式运行,负荷跟踪期间需要调整堆芯硼浓度。受硼回收系统能力限制,仅在85%寿期内具备负荷跟踪能力。为改善177燃料组件堆芯反应堆负荷跟踪能力,扩大可进行负荷跟踪的寿期范围,基于177燃料组件堆芯进行了机械补偿控制策略的研究。设计了不同控制棒组布置方案,从控制棒组价值、对功率峰的影响、负荷跟踪过程中控制能力等方面进行了分析。基于优化的控制棒组布置方案和机械补偿控制策略,进行了全寿期基负荷运行、90%寿期末日负荷循环负荷跟踪以及启动过程模拟。结果表明,在适当的控制棒组布置方案下,177燃料组件堆芯可实施机械补偿控制策略,负荷跟踪能力达到了国际先进水平。 相似文献
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增殖燃烧一体化快堆插花式倒料方案研究 总被引:1,自引:1,他引:0
增殖燃烧一体化快堆利用快堆的增殖特性,通过倒料完成从增殖组件向燃烧组件的过渡,从而实现增殖和燃烧过程的一体化。全寿期内燃烧组件提供堆芯的绝大部分功率,而在燃烧组件周围的贫铀组件则将其中的238U转化为239Pu,实现增殖功能。通过定期倒料,堆芯在一次装料后可实现长期自持临界,维持几十年的稳定运行。合理的堆芯布置与倒料方案可更好地平衡燃料的燃烧和增殖过程。插花式的堆芯布置与倒料方案是将一部分增殖组件分散布置在堆芯高通量区,保证了增殖组件的快速增殖,同时可保持堆芯在整个反应堆寿期内具有稳定的功率分布。另外,插花式堆芯布置与倒料方案最终的组件卸料燃耗是相对均衡的,所有从燃烧区倒出的组件均具有相近的燃耗,一般在250~300 GW•d/t左右。这使得增殖燃烧一体化快堆可在不进行燃料后处理的条件下,实现铀资源的高效利用。 相似文献
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状态报告是核电厂开展经验反馈的基础,通过学习和借鉴核电厂状态报告管理方法可以完善高通量工程试验堆(HFETR)的经验反馈制度,提高HFETR运行的安全性和日常运营管理水平。本文首先对核电厂状态报告体系开展了初步的分析;然后结合HFETR运维管理水平分析了相应的状态报告实施策略和组织接口,建立了HFETR状态报告事件分级准则,并完成了相关事件分级工作;最后本文为HFETR实际实施状态报告开发出模板,建立了状态报告流程,并提出了后续工作的重点内容。本文的研究为推动HFETR建立状态报告管理体系奠定了基础。 相似文献