共查询到19条相似文献,搜索用时 140 毫秒
1.
三种堆型核燃料循环经济性比较 总被引:1,自引:1,他引:1
本文详细地分析了压水堆、高温气冷堆、快堆三种堆型核电厂的燃料循环过程,建立了燃料循环费用的计算模型和灵敏度分析模型。对三种堆型的核燃料费用进行了分析比较,指出快堆是燃料费用最经济的堆型。 相似文献
2.
简要叙述了先进堆型模块式高温气冷堆(MHTGR)、先进沸水堆(ABWR)和中国实验快堆(CEFR)的良好安全特性并给出了它们某些系统和设备安全级别与现行压水堆PWR和沸水堆BWR的比较。据此,并通过对CEFR三回路、通风系统和柴油发电机组等安全功能的分析,从而对它们的安全分级提出了建议。 相似文献
3.
4.
基于模块式高温气冷堆先进技术和超临界蒸汽动力循环先进技术,研究了高温气冷堆模块与超临界蒸汽动力循环耦合配置方案。结合超临界热力循环理论及模块化高温气冷堆的特性,研究了超临界热力循环方案及相应的循环参数。针对标准一次再热循环,研究了反应堆模块与汽轮机组匹配模式;计算了循环可能达到的效率,并与先进压水堆效率进行了比较。结果表明:模块化高温气冷堆超临界循环效率比压水堆电厂约高30%。本研究结果可作为高温气冷堆超临界循环电站概念设计的理论基础,为进一步的技术研究与方案设计提供依据。 相似文献
5.
本文对模块式高温气冷堆的棱柱状和球床两种堆芯型式和一体化与肩并肩分置式两种总体设计方案分别进行了技术特点、设计制造、运行经验和安全性与经济性的比较,提出了在我国发展高温气冷堆的堆型选用原则和建议. 相似文献
6.
7.
对聚变-裂变混合堆的安全性进行了初步分析和探讨。主要利用改进后的混合堆放射性程序FDKR对混合堆产生的核废物及放射性进行计算,并将结果与压水堆、高温气冷堆和液态金属冷却快中子增殖堆进行了比较。结果表明,混合堆与裂变动力堆相比有较好的安全性。 相似文献
8.
气冷快堆兼具高温气冷堆的经济性和快堆的可持续性等优点,在四代堆型中具有独特的技术优势。为了适应气冷快堆高温、高中子通量的堆芯环境,本文基于耐事故燃料模型,提出了一种块状气冷快堆燃料组件设计方案,并对该组件中铀钚混合燃料中的钚含量、冷却孔道的直径及数量、栅距比、包壳及组件盒厚度等物理参数对中子学特性的影响规律开展了敏感性分析研究。分析结果表明:在研究的6个参数中,钚含量和栅距比对组件的中子学特性影响最大,冷却孔道数量主要影响组件内的功率分布,其余参数对组件中子学特性几乎无影响。最后针对块状燃料组件低冷却剂份额的特点,利用单通道模型进行组件内的温度分布计算,给出了热工限值对组件参数的要求。 相似文献
9.
徐 《中国原子能科学研究院年报》2006,(1):3-4
2000年首先由美国提出、2001年众多核能国家认可的第4代先进核能系统(简称“第4代”)共推荐了6种堆型,即钠冷快堆、气冷快堆、铅冷快堆、超临界水堆、超高温堆和熔盐堆。它们的技术基础不同。世界上钠冷快堆曾建造18座,从实验快堆、原型快堆、直到经济验证性快堆, 相似文献
10.
11.
Reactor cores of PWR and LMFBR, loaded with different commercial and emerging nuclear fuels, have been simulated and compared at BOI with respect to criticality with and without chemical shim, control rods and sodium. The different cases considered, within each of the reactor types, are grouped together according to their fissile content, when compared on the basis of the neutron multiplication factor (keff). For both PWR and LMFBR reactor types, the reactivity worths of the control rods do not change significantly when replacing commercial fuels by emerging ones. In the case of the LMFBR, the Na void reactivity effects are small and comparable using either emerging or commercial fuels. Hence, operation and control of the core at beginning of irradiation are similar for emerging or commercial fuels. 相似文献
12.
压水堆核电厂控制系统仿真研究 总被引:1,自引:1,他引:0
提出了用于压水堆核电厂控制系统快速和精确仿真的系统数学模型和数值方法,并用研制的仿真程序NCS对商用压水堆核电厂控制系统进行了仿真研究,得到了满意的结果。 相似文献
13.
14.
Economic potential of modular reactor nuclear power plants based on the Chinese HTR-PM project 总被引:4,自引:0,他引:4
Modular reactors with improved safety features have been developed after the Three-Mile Island accident. Economics of small modular reactors compared to large light water reactors whose power output is 10 times higher is the major issue for these kind of reactors to be introduced into the market. Based on the Chinese high temperature gas-cooled reactor pebble-bed module (HTR-PM) project, this paper analyzes economical potentials of modular reactor nuclear power plants. The reactor plant equipments are divided into 6 categories such as RPV and reactor internals, other NSSS components and so on. The economic impact of these equipments is analyzed. It is found that the major difference between an HTR-PM plant and a PWR is the capital costs of the RPV and the reactor internals. The fact, however, that RPV and reactor internals costs account for only 2% of the total plant costs in PWR plants demonstrates the limited influence of this difference. On the premise of multiple NSSS modules forming a nuclear power plant with a plant capacity equivalent to a typical PWR plant, an upper value and a target value of the total plant capital costs are estimated. A comparison is made for two design proposals of the Chinese HTR-PM project. It is estimated that the specific costs of a ready-to-build 2 × 250 MWth modular plant will be only 5% higher than the specific costs of one 458 MWth plant. When considering the technical uncertainties of the latter, a 2 × 250 MWth modular plant seems to be more attractive. Finally, four main points are listed for MHTGRs to achieve economic viability. 相似文献
15.
压水堆(PWR)是目前核电厂反应堆的主力堆型,而核燃料是反应堆的能量源泉和放射性裂变物质的主要来源,关乎核电厂的经济性和安全性。本文对当前国际上面向商用PWR应用研发的掺杂UO2燃料、高铀密度燃料、微封装燃料和金属燃料的性能特点、技术状态及前景进行了归纳和评价。在掺杂UO2燃料中,大晶粒燃料具有较高的技术成熟度,将在PWR实现大规模商用;高铀密度燃料和金属燃料在高温水腐蚀氧化问题以及事故下的行为仍待研究解决;具有极致安全的微封装燃料更适合特殊用途的小型反应堆。应协同开展先进燃料组件设计、建立设计准则以及研发高保真的性能分析技术等,以充分发挥新型燃料的可靠性及高燃耗优势。 相似文献
16.
《Journal of Nuclear Science and Technology》2013,50(7):692-701
Abstract Whole core calculations have been performed for a commercial size PWR and a prototype LMFBR by using vectorized Monte Carlo codes. Geometries of cores were precisely represented in a pin by pin model. The calculated parameters were k eff, control rod worth, power distribution and so on. Both multigroup and continuous energy models were used and the accuracy of multigroup approximation was evaluated through the comparison of both results. One million neutron histories were tracked to considerably reduce variances. It was demonstrated that the high speed vectorized codes could calculate k eff, assembly power and some reactivity worths within practical computation time. For pin power and small reactivity worth calculations, the order of 10 million histories would be necessary. It would be difficult for the conventional scalar code to solve such large scale problems while the present codes consumed computation time less than 30 min for a PWR and 1 hour for an LMFBR. Required number of histories to achieve target design accuracy were estimated for those neutronic parameters. 相似文献
17.
为建立基于现场可编程门阵列(FPGA)的反应堆保护系统的可靠性模型,以对系统安全提供有效的分析与验证手段。本研究采用故障树、随机Petri网模型,对CANDU堆1号停堆系统(SDS1)单通道进行可靠性建模与分析。对故障树模型分析得到最小割集,以顶事件发生概率作为系统故障概率,在考虑故障检测、维修与定期试验情况下对随机Petri网模型进行仿真得到系统的拒动概率。研究结果表明,故障树和状态空间方法存在一定局限性,随机Petri网能够反映故障检测与定期试验对反应堆保护系统的影响,可以动态地反映系统可靠性,并且避免了状态空间爆炸问题。因此,本研究建立的随机Petri网模型适用于反应堆保护系统的可靠性建模。 相似文献
18.
在分析M310堆型核电站辐射屏蔽设计中由于工具限制存在的问题以及“华龙一号”堆型核电站辐射屏蔽设计提出的要求的基础上,从程序界面、输入接口、计算功能和辐射场应用扩展4个方面提出先进压水堆核电站辐射屏蔽优化设计对于蒙特卡罗(MC)方法的要求。MC方法在“华龙一号”辐射屏蔽优化设计的应用实践表明,基于MC方法的计算程序在程序界面、输入接口和辐射场应用扩展方面进一步提升之后,可在先进压水堆核电站辐射屏蔽优化设计方面发挥巨大的作用,显著提升核电站辐射屏蔽优化设计的水平。 相似文献